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Atomic FISSSON PRODUCT DATA FGi THERMAL REACTORS W.H. WALKER Chçjtk River, Ontario . December I9ÔV ' , . ' ' , " Port I

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Page 1: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

Atomic

FISSSON PRODUCT DATA FGi THERMAL REACTORS

W.H. WALKER

Chçjtk River, Ontario

. December I9ÔV

• • ' • • , . ' ' , • "

Port I

Page 2: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

FISSION PRODUCT DATA FOR THERMAL REACTORS

Part I - Cross Sections

by

W.H. WALKER

AECL-3037Part I

Page 3: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

FISSION PRODUCT DATA FOR THERMAL REACTORS

Part I - Cross Sections

by

W.H. WALKER

A B S T R A C T

Part I is a compilation and evaluation of cross section

measurements for all fission products with half-lives exceeding

~ 5 h in the mass range 76 to 165. Resonance integrals,

2200 m/s cross sections and reactor spectrum cross sections

are included. Resonance integrals computed from resonance

parameters are included in the resonance data if available.

A set of recommended cross sections and resonance integrals

is also given for use in the FISSPROD data library.

APPLIED MATHEMATICS BRANCHChalk River Nuclear Laboratories

December, 1969AECL-303 7Part I

Page 4: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

AfcCL-3037

Données relatives aux produits de fission pour les réacteurs thermiques

1 Partie - Sections efficaces

par W.H. Walker

Résumé

F* T* P*

Cette I Partie est une compilation et une évaluation

de mesures de sections efficaces pour tous les produits de

fission dont les demi-vies excédent 'v 5 h dans l'intervalle des

masses allant de 76'à 165. Des intégrales de résonance, des

sections efficaces de 2200 m/s et des sections efficaces de

spectre sont incluses. Les intégrales de résonance calculées

« partir de paramètres de résonance sont incluses dans les

données de résonance, si elles sont disponibles. Des séries

de sections efficaces et d'intégrales de résonance sont

recommandées pour la bibliothèque des données FISSPROD.

L'Energie Atomique du Canada, Limitée

Chalk River, Ontario

Décembre 1969

Page 5: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 1 -

1. INTRODUCTION

1.1 Estimates of Fission Product Absorption at ChalkRiver

There has been a continuing interest at Chalk River

in accurate estimates of fission product absorption dating

back to 1951 (Hurst), then proceeding to the inclusion of

;3-decay hold-up and secondary (capture) products (Walker,

1956), the representation of fission product capture by

pseudo-fission products (Hurst (1957 ); Hurst et al (l'JSH))

and the inclusion of opithermal absorption (Walker, l'tMj) .

The last report and two subsequent extensions (Walker,

1962, 3 964) presented tabulations of both yields and

cross sections, but also calculated yields for fixed pseudo-

fission product cross sections. With the acquisition of

the G-20 computer at Chalk River it was felt that a more

detailed fission product representation was possible

which could be used to check experimental results as well

as the range of validity of various simplified représentatif

such as the pseudo-fission products.

This program, FISSPROD, was oriqin.il.ly prepared

in 1963 and hos now been written up (Lane, I'M/i).

It has been tested regularly in the interval using an

interim set of yields and cross sections based pr:mtni/

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- 2 -

on the 1964 compilation (Walker). The purpose of the

present compilation and evaluation is to present a defini-

tive and well-documented set of data for FISSPROD which

may be useful to others. The review covers yields from

mass 76 to 160 for both thermal and fast neutron fission

and cross sections and resonance integrals of the nearly

200 fission products with half-lives greater than about

5 hours that are treated specifically in FISSPROD.

1. 2 }3-Decayj Isomeric Transitions and Neutron Capture

There is little similarity between the nuclide

concentrations of the fission fragments formed in the fission

process itself and the nuclide concentrations found in

reactor fuel near the end of its life. The fragments are

almost all radioactive , with a most probable charge 3-4

unies from the most stable charge for a given mass and

a negligible probability of being stable-. These undergo

a "chain", of J-decays that transform them to long-lived

or stable nuclides, and many of these subsequently

capture a neutron. Only those transmutations involving

the capture of a neutron are reviewed here. Of the

remaining data, half-lives are taken from the "Table

of Isotopes" (Lederer et al (1967)) and branching ratios

Page 7: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 3 -

from Cenacchi's 1968 review of fission product data.

The nuclides and transmutations included in FISS-

PROD are shown schematically in Fig. 1 and cross sections

and resonance integrals are listed in Table 1. Several

compilations and evaluation of cross section data have

appeared since work on the FISSPROD library began and ha'. >

been very useful as a check on tho completeness of the

data. These are:

( a) CINDA *-

A bibliographic listing which includes references

for the types of data of interest here. Some of the

references given in the present survey do not appear in

CINDA, and some given there are not included here, the

usual reason being that if a result has appeared more than

once in the literature it is given only once in Table 1

(usually with its most recent reference). Also values from

progress reports are omitted unless their inclusion is

essential to a satisfactory evaluation.

(b) BNL-325, 2nd Edition, Supplement 2 (1964-bb)

An extensive coverage of new thermal cross section

and resonance parameter data with thorough documentation.

Page 8: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

_ 4 ~

It does not cover the fission products completely since it

is a supplement, but many entries in the 2nd edition and

supplemeiv 1 are included in supplement 2 for comparison

with more recent results. Only a few resonance integral

measurements are covered.

(c) Twenty-Two Hundred Meter per Second Neutron- * 1—. ' • •

Absorption Cros.? Sections

A compilation by Goldman et al (1969) which gives

a complete list of evaluated thermal cross sections from

hydrogen to fermium. Its purpose is to present in one

report", and at the same time to up-date, ail BNL-32 5 thermal

cross sections. References are given for the measurements

on which each cross section evaluation is based,

(.d) A Compilation of Nuclear Dataon the ThermalFission Products of L" '*° , U~ '"" and Pu3 '"3

This survey by Cenacchi (1968) includes the fission

product decay chains in the diagrammatic form used by

Katcoff (1960) with revised branching ratios and half-lives,

and a set of yields, half-lives, thermal cross sections and

resonance integrals taken from a variety of earlier compila-

tions supplemented by the results of more recent measurements

Page 9: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 5 -

2. PRESENTATION OF DATA

2.1 Figure 1 (p. 93)

This "chart of the nuclides" indicates by arrows

the (3-decays, isoraeric transitions and capture transmutations

included in the FISSPROD library or program. The chart

differs significantly from the standard representation

in its treatment of short-lived isomers (T- <• b hu.u's)

indicated in the chart by brackets. These do not appear

in the FISSPROD library but are included m the program

by assuming that they decay promptly by ;- -emission to the

ground state of the daughter. Thus any branching which

may occur in the decay of a short-lived isomer must be

taken into account by modifying the production modes. For

example, suppose a metastable state that is short-lived

(and therefore omitted from the FISSPROD library) ;;:.dc:r'jo«.-.H

only isomeric decay. Because the program assumes that

it ^-decays instead, it is necessary for the purposes of

FISSPROD calculations to make the effective cross section

to the metastable state zero, while that to the ground

state is equal to the sum of the cross sections to the

ground and metastable states. As far as the calculations

are concerned this metastable isomer is never formed,

Page 10: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 6 -

so that its omission does not introduce any significant

error in the calculation. Branching ratios which differ

from 100% and 0% are discussed in the description of

Table 1 under the heading "Columns 3-6".

2.2 Table 1 (pp 19-88)

Table 1 lists all fission, products, including

metastable isomers, from mass 76 to 165 having half-lives

greater than -. 5 hours. In addition many of the short-

lived nuciides with T. < 5 hours arc included with thoir

half-life and branching ratio (but without a cross section

assignment) to clarify the choice of partial cross sections

and simplify the problem of following capture/decay sequences

The contents of the table are described below by

columns :

Column 1 ("Reference")

Heading Each nuclide is identified by an entry inthe reference column of the form

Z - chemical symbol - A i (T±)

where i = m for metastable statei s g for ground state

or is omitted where only the ground stateis of interest. T^ is the half-life ofradioactive nuclei in seconds (s), minutes(m), hours (h), days (d) or years (y).

Page 11: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 7 -

References

ResonanceParameters

Numbered entries are in order of date ofpublication. The journal notation followsCINDA usage for the more common journals,but is written out more fully for others(e.g., En Nucleare for Energia Nucleare).Report numbers are those given on thetitle page. The originating laboratoriesare listed in CINDA. Data from fourconferences are also included, vi;\

PIC-1 - the 1955 Geneva Conference on tk<peaceful uses of Atomic "ncr^y

PIC-2 - the ïUJ8 Geneva Cunierence

Paris - the proceedings of the ! •»,>, 1AKAConference on Nucle.ir p-.ta U TRc-.ictors held in Par , s '2 vois .'

NBS Spec. Pub]. 200 - the l'.u>:> Wash i.n-jton

Conference u: i la'alron Cross; S vet i u .:and Toi-hnolc-iy (2 vols.) .

Indicates values of the thermal contributionand resonance integrals calculated frompublished resonance parameters. The refer-ence BNL-325 alone indicates the five-part2nd supplement to the 2nd edition ( iy<j4-lot.(j)Earlier versions of DNL-J2C. are indicatedby a bracketed date. Other sources areindicated by journal reference without

Column 2 ("Method")

Entries here indicate the general method used to obtainthe data. These are-.

Act

Crys Spec

By activatior using either ;:>- or ,-cuuntmgwith or without cadmium-shielded samples.

From total cross section measurement at2200 m/s using a crystal spectrometer.

Page 12: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 8 -

Mass Spac From mass spectrometric comparison ofirradiated and unirradiated samples.

Pile Osc From pile oscillator comparison of theunknown absorber to a standard. Thermaland epithermal absorption can be differen-tiated by measurements in neutron fluxeswith different epithermal components.

Pulsed n From rate at which neutrons injected in apulse in a volume containing the unknownabsorber disappear.

React From reactivity measurements using changein critical height or period of a calibratedtest reactor.

From total cross section measurement at2200 m/s using a fast chopper.

t of f

Columns 3-6 (Cross Sections and Resonance Integx'als)

The Westcott convention (Westcott et al, 1958) is usedthroughout with modified notation.

Cross SectionNotation

A

o0

o

go

effective cross section in a fluxgiven by nvo (n is the total neutrondensity and vo = 2200 m/s

the cross section at 2200 m/s

the nv0 cross section in a Maxwellianflux. Although cadmium difference valuesinclude the contribution of the epithermalspectrum below the cadmium cutoff, thisis small compared to ga if there are noresonances near the Cd cutoff energy.These measurements are therefore designatedas go in the table since in practice thedifference between ct^ and ga is muchsmaller than the errors.

Page 13: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 9 -

Subscripts

Isomers

g is a function of T, where the latter isnot usually specified accurately in theexperiment. For a 1/v absorber q - 1for all T.

I The reduced resonance integral, that iswith the 1/v component subtracted, takenover the whole epi-Maxwellian spectrum.

RI The resonance integral above the cadmiumcutoff. The latter is assumed to be0.55 eV unless otherwise indicated,

ab Absorption (from oscillator, reactivitytime-of-flight and crystal spectrometermeasurements, where the two latter are totalcross sections corrected for scattering).

ac Activation

c Capture (from mass spectrometer measure-ments) .

t Total (absorption & scattering from time-of-flight and crystal spectrometer measurements)

(m) indicates cross section to mctastable or(g) ground state respectively .

An asterisk beside g or m (g* or ra*) indicatesan effective cross section where a short-livedisoraeric state formed in capture decays byboth isomeric transition to the ground state and .•emissions. The total cross section A(g)+*(m) hasto be reapportioned to take account of the factthat FISSPROD assumes that short-lived nuclidesdecay by (3-emission only. The new cross sectionsare designated as ~(g*) and ^(m*) andj(g*) + :(m*)= j(g)+ " (m) . For example, considerGe 7 6, with g°ab(m)= 0.10 b and g°ab(g)- 0•

06 b-Since Ge 7 7 m has a half-life of 54 s it is notincluded in the data library, and the programassumes 100% decay to As7'g. Because 24% of G<decays isomerically to Ge'/g the Ge'" absorptioncross sections must be corrected to give etfectivivalues for use in FISSPROD -

gaab(g*) = 0.06 + 0.24 x 0.10 to = 0.08., b:

similarly g°ab(m*) = 0.07« b.

ni

Page 14: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 10 -

Resonance ^°ab> 1

ah a n d ^b-unr a r e calculated from

Parameter published resonance parameters for the rangeCalculations of resonant energies indicated in the comments

column. The computer program uses approximateformulae for A° a b and I a b derived on the assump-tion that the resonance energy is above thecadmium cut-off. The formulae are

, = :•: 4.09 g. r . " . (i + ^ ) E .ab x l ni ti E r i n

4090 g. ? .

"ab ~ •; E ."ri

.002

tE •

ri 1 ri

where g. is the statistical weight factor of theith level.

is the neutron partial width of the ithlevel, in meV.

" . is the radiative partial width of the: ith level in meV.

E . is the neutron energy at the peak of theith resonance in eV.

kT is the mean energy of thermal neutronsin eV.

and .;kT is the effective cut-off for the 1/Eepithermal spectrum. (here h: is assumedequal to 5) .

The expression for jj , is an approximation to the

Breit-Wigner cross section at 2200 m/s and that for Iat) is

adapted from an expression originally derived by Story (1957)

•'•ab-unr ^s t^ie estimated contribution to I of

unresolved resonances. The derivation assumes equal level

spacing and s-wave capture only, the two assumptions

Page 15: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 11 -

introducing errors of opposite sign which tend to cancel. A com-

parison between an earlier estimate using the same equation

(Walker, 1960) and more recent results where more level parameters

are available indicates that the formula tends to overestimate

the unresolved contribution. it is assumed that the error in

I , is not greater than the estimated value.ab-unr

When data from 3 or more levels are available the level

spacing and reduced neutron width are deduced from the listed

parameters. When only 1 or 2 levels are known a strength function

is assigned, but if no levels are assigned to the nuclide I ,ab-unr

is assumed to be zero. I is obtained by integration over theab-unr

energy range from the last resolved level to infinity, except

where energies assigned to resonances of other isotopes measured

in the same experiment, indicate a wider energy coverage, from

which it is inferred that there are no unidentified peaks over

this range and the lower energy limit is raised accordingly.

Columns 7, 8 ("Ratios")

Ratios of I/go deduced from cadmium ratio measurements

and j(g)/o(m) are listed here. All ratios are measured by

activation so no subscript is included.

Column 9 ("Commenta")

Renormalization Most cross sections have been measuredrelative to some standard. Where thecross section of the standard is quoted

Page 16: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 12 -

the measured cross sections have beenrenormalized to the values given below.

Standard

Harwell B(oron)

B

CO69

Eu

Gd

Ho

Au 1 9 7

0

°ab

771

7 59

37.2

u4

98.8

Value

AQab

4400

49000

I a b

58.

151

in

5

3

Barns

RIab

75

1558

i/S

15.3

Other Corrections-The activation results of Seren et al(PR 7_2, 888) were corrected for naturalabundance, half-life and decay schemein addition to normalizing to the newstandard.

-The cadmium ratio results of Harris etal (PR T2-> H ) w e r e corrected for reson-ance self-shielding when sufficientinformation on sample size was provided,and were also renormalized to the newstandard.

- Other comments are intended to beself-explanatory.

Recommended Values (Columns 3-6)

The values recommended are obtained using the followingguide lines unless there is a comment in the last columnindicating a preferred value or another procedure.

Page 17: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 13 -

(1) If results are in reasonable agreement a weightedaverage is estimated, weighting inversely as thestated error.

(2) If one value diverges markedly from the remainderit is assumed to be a flyer and is omitted intaking the average.

(3) Since values of t^°^ are estimated only for reallevels (Er ^0.5 eV) and take no account of thecontribution of virtual levels it is not used u>averaging, but serves only as a check (all measuredthermal values should be '5> L° ) .

ab(4) If °at) from a time-of-flight or crystal spectro-

meter measurement is significantly greater thanall integral values and if it is obtained usingan oxide sample, it is assumed that it is m crruidue to water contamination or small-angle scattering

(5) If measured integral values of I or RI aresignificantly less than I calculated fromresonance parameters it is assumed to be a self-shielded value, (unless sufficient data isprovided to indicate otherwise) and omitted intaking the average.

(6) If only a measured upper limit is available therecommended value is half the upper limit roundedoff (upwards) to the same number of significantfigures.

(7) If no measured thermal data is available, butresonance integrals give a value of AJa^, thenthe recommended °ak is based on the latter. Acomparison of ^y, with &9

ab indicates that theratio of the two varies from less than unity to~ 10 3, with median values of 1 to 4 and averagevalues from 1-10 depending on the magnitude ofAo a b. The two recommended values listed below arechosen to be roughly mid-way between median andaverage valae.

Page 18: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 14 -

Sr8 7

10.7

40 •

Pd105

2 . 2

10

Nue 1 i.de

Calculated û° a t )

Recommended a^

(8) If no data at all are available the recommendedvalues are estimates based on the 3 . and Iaj_)values for nuclides in the same mass range, dividedaccording to whether they are even Z-even N, evenZ-odd N, or odd Z. As in the case discussed abovevalues cover a wide range with a bias towardssmaller values so that the median is significantlyless than the average. The recommended valueslie between these two. Most "unknowns" are radio-active, and in this case, the choice of 3 -̂ is notimportant if °at>0 « X. Only in the high massrange, do the average and median values becomesignificant by this criterion, with a value of. -".. 50,000 b for even Z, odd N nuclei, and ̂ 2000 bfor odd Z nuclei. The nuclei of interest are47-h S m U 3 , 18-h G d l b % 15-dEu l b G and 15.2-hEu1;i . For the first three nuclides :0 ~ X if5 - lO1'1

is used.10il n/cnT s and the "average" cross section

In the case of Sml03 a significant capture ratewould decrease the equilibrium concentration ofSmlba and enhance the yield of Sm154 ( g S ^ = 5b)relative to Eu 1 & 3 (°ab ~ ̂ 50 b ) " . a significantdifference between yields measured using high andlow flux irradiations might be expected. Unfor-tunately the only measurement of this kind(Bidinosti et. al. (1958)) did not extend pastmass 152. Comparison of other yield measurementsgive conflicting results or are inconclusivebecause of lack of information on irradiationconditions.

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- 15 -

For Gd159 the yield is so small (zero ir. FISSPROD)that the effect will not be significant.

In the case of Eu1"6, the decay product isGd (9°ab ~ 1.4b) while capture yields Gd1r '[oah = 264,000 b)-. Eu 1 5 6 is formed not only as a"primary" fission product but also from captureby Eu1'55 ($ ^ 4,000 b) . The possibility thatEu 1 5 b has a 2.000 b cross section thereforerepresents a significant uncertainty in newtronabsorption in high flux reactors.

The "recommended" cross sections are:

TYPE

even-even

even-odd

odd Z

77

h -

30b-

1.0b

90

•4

-T5.

100

.... -1

- 5

110

,0b —

. 0b -

MASS,

120

-HlOObr-

A

1

10b-

30

T

140

4-

50b

15b -f30

150

3

. ,

lbO

,0b -

50 kb-

2 kb *-

These appear inside brackets in Table 1 in theappropriate column. In view of the uncertaintyin these values they are assumed to be reactorspectrum cross sections C?ab) and no estimate ofthe resonance integral is made.

2.3 Table 2 (pp 89-92)

;. Table 2 is a listing of the FISSPROD nuclide table.

Following the identifier (A,Z,E) (E=0 indicates a ground

As t a t e , E = l a m e t a s t a b l e i s o m e r ) ga(m) ( o r J(m)), I ( m ) ,

Aga(g) (or a(g)) and I(g) are given in barns, and then the

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- 16 -

:. cav constants for isomeric transition to the ground state

v;;o jhangc in Z) and for ^-decay (Z -" 7, + 1) to the isomeric

and ground states. The latter are in units of 10"" s (k*)

e--o that , -j>>- J flux of 10""1 n/cm" s, •*•*/: is in barns and

•h- listed value3 can be compared directly with cross sections.

This Deraus a quick estimate of the relative importance of

::•• \ivy.- Mpt.:ri ind :--decav for any in.clido. The letter U

!•:.; lovi"..i a thermal en. s'̂ section or resunan-co integral

niciicati'G fh.r. the cross section is unknown and the value

.!.s the estimated one ijiver; in brackets in Table 1 . In the

i'IFSPRGD program neutron absorption by nuclides with "U"

th-Tn'.al cross sections is summed separately from that for

y. .. i'ld.-K with known cross .sections. One of the control

:• !•.--'..TV* ers in l-'ISSl-'ROn permits all the cross sections of the

'i" ii'oup tc bt_ increased or decreased by a common factor.

r.i.t- that the large "unknowns" (estimated as 2,000 b or

-< iter) do not have the "U" and therefore are independent

•jf th«.' parameter control I ing the magnitude of the "U" cross

••'-'tKnis, These are listed in the yield table with an

indicator which assigns them to a "large unknown cross section1

•jroup.

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- 17

3. ACKNOWLEDGEMENTS

I would like to thank Dr. Norman Holdcn of Knolls

Atomic Power Laboratory for a careful revue of the oriyinai

version of Table 1 which resulted in the elimination c,I many

errors.

4 • REFERENCES

Cenacchi , G., "A Compilation of Nuclear Dit a on th-- Tin. : r.\ ..

Fission Products of U-2ij, V~21CD and !'::-JJH" CNf.N / Hoi >>...•)<

Report no. RT/FIMA( f>8) 4 .

Gold.man, D.T., Aline, R., Sher, R., Stehn, J.R., "22uU m/:

Neutron Absorption Cross Sections" subt.';' tud Lu N;.ch-.ir

Data (1969).

Hurst, D.G., "An Estimate of tho Total Cross Soctm:. ut

Accumulated Fission Products" AL'CL Report no. M H (Ci-.G i- :' "

(1951)

Hurst, D.G., "Calculated C o s s Sections of l r r u h : •'-••! • . •-; : :

Products" AECL Report no. J4b ( CRKP-(. V ' ) ( i ' < ' ~ ) .

Hurst, D.G., Kennedy, J.M. and K I I O T , K.H., "Ci •- '• * : :

and Yields of Pseudo-Fission Pri.d idt " Aie: !,••[" it •. .

(CRRP-760) (1958) .

Katcoff, S., "Fission Product Yields t rwin Ne,i run i:..i..'i

Fission" Nucleonics JJî (11), 2u\ ( I'M,.') .

Lane, (Mrs.) F., "FISSPROD, A G-JU Cnm[r,.t.T IT.-jru-..11 ;:K\.

(1969) .

Lederer, C M . , Hollander, J.M., Périmai,, I,. T .1 l>':: • •'- 1 s. '. >:

6th éd., Wiley & Sons (1907).

Story, J.S., UKAEA Report no. AERE T/R 2\H'> (!•>•') ( f ti ,-

expression for I(E) is also yiviTi by Wrstrutt . •, .: . N • • .

En. _2, 59 (1955) .

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- 18 -

Walker, W.H , "Fission Product Accumulation" AECL-309 (CRRP-634)(1956) .

Walker, W.H., "Yields and Effective Cross Sections of FissionProducts and Pseudo-Fission Products" with an appendix byS.A. Kushneriuk, AECL-1054 (CRRP-913)(1960).

Walker, W.H., "Fission Product Poisoning from the Fast Fissionof U-238" AECL-1537 (CRRP-1090) (1962).

Walker, W.H., "The Effect of New Data on Reactor Poisoning byNon-saturating Fission Products" AECL-2111 (CRRP-1185)(1964).

Westcott, C.H., Walker, W.H., Alexander, T.K., "EffectiveCross Sections and Cadmium Ratios for the Neutron Spectraof Thermal Reactors". Proceedings of the 2nd GenevaConference 16, 70 (1958)(AECL-612).

Page 23: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

TABLE 1 - F1S..10N PRODUCT DECAY AND CROSS SECTION DATA

1.

2.

REFERENCE

32-Ge-76

ponerance, PR B_8

Lyon ,

1056

Eldridge,

( 57 )

, 412 (52)

PR 107,

P

METHOD

pile osc

act

3. des Mateosian, Goldhaber

PR 108. 766 (5')

4 . Weiomar.fi Z? lb~ , 5-J9 (b2)

5. M a n n h a r t , vonach ZP 2 1 0 ,

1J 1 6 B I

Resonance P a r a m e t e r s BNL-325

£ YMB.

1Jal.-

V- In l )

-ràc(m)

< 3 ° a c l m ;

VALUE

0 . 3 6 i 0 . 0 7

• j . 1 3 ^ ' J . C l l

0. 00b

.... .,* * ; . ; . 5

J.07t-.ru. :] 5

0.12 T 0.03

j . 0 8 b r 0.01)9

4.

RESONANCE

SYMB.

a b

SW.H.

( q ) ,' • lm)

AU S t d .

R c d ( C O ) = 1 0 l r T/T = 0 . 0 5 )

By Cd d i t t . R c d = 3 . 2 5 f o r

b o t h l s o m e r s . Y i e l d of

Ge-77q c o r r e c t e d f o r IT

G . 5 1 r J . 0 3

0 . O b O i O . J i ' t I For En > 3 Kev

I

RECOMMFNDED

^ " a L l m l

qV,M«! '

j . 10

J i - G e - : ' K IS4 s . IT 24%!

3^-Ge- " . 1 . 3 h r '

I 3B.- hr

30;

|_. .

IabIm)

l a b U )

J. 52

Res, i n t . estj-jnated frcçr,Rccj of ref 1 assiJiTiti;r Y/T T L'. i)t I Brookhaverr e a c t o r Corel

Not included ir.

i i _». i

I

L

I4o c ross st."'. n r . da taavai lable 1

No c ros s sf * . r. d a ' sa v a i l a b l y

i

Page 24: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

34-Se-77

1. poraerance PR 88, 412 (52)

Resonance parameters BNL-325

RECOMMENDED

34-Se-7B

1. Pomerance PR 88, 412 152)

2. Hans et al NP 2_0. 183 (60)

3. Kramer, Wahl NSE :22., 376 (65)

4. Weigmann ZP 16_7, 549 (62)

5. Mannhart, Vonach ZP 210.13 (68)

6. Ricabarra et al CJP 46,2473 (68)

Resonance parameters BNL-32 5

RECOMMENDED

34-Se-79:rt (3.9 m, IT 100%>

i METHOD

pjle ose

piie ose

act

act

act

act

act

THERMAL

SYMB.

9°ab

^'ab

y°ab

g°ac(m)

g°a-(m)

-"ab

,\,b

VALUE

42 t 4

1 . 2 b i j . 1 f

42

0 . 4 t U . 4

•i. 12 tO. 04

0 . ;6t'j. 04

0.40i 0.0-1

0 251*0.u25

0.3,0.1

i

0.4

RESONANCE

ISVMD.

lab

^ ab-unr

l j b j n r

VALUE

RATIOS

r-YMi) VALUL

13.4rl.i

U. 3

- -

l/g° (10.7j

i

6 r 2

0.1

4.C

i/g- ; a.yto.i

1

CUHMEN1'

Au std.

Au std.

Au Btd. Rc(j(Au) = 3.6(r/T/Tu~0.021) I/g^ fromRcd(Se-78)

Au std.

Resolved res., 380 to 9880eV: max. contrib. from380 eV (98%)

Assuming °(g)/°(m)-~ 0.1

Not included in FISSPHOD

O

Page 25: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

34-3e-79 (b.5 x 10* / r . )

34-Se-ao

1. Seren et al PR 72, B88 (47)

METHOD

act

S Y

A

ab

THERMAL

2. Sunyar, Goldhaber PR 76,180 (49)

3 . Pomerance FR Bji, 412 (5 )

A. A p e r s e t aJ J1NC j ; , 23 ! 571

5. K e i s c h PR 1_2_1, 7h9 1 ti J )

ti . B i s h o p >.•». a i KP bÇ, 241 ( b4 )

7 . M n n n h a r t . Vo:ui. ,i .'P i l ! , IS

VALUE

RESONANCE

SYMB . VALUE

130)

i

pile ose

'."' . 4b : n . 1 1

(m) J.Ù34TO.U'J7

g • U . b l • L . :_.!'

HI

SYMB. VALUECOMMENTS

. i ). • . U-j-1

' ( .T ) ° I ) 1

fi. Ricabarr.i et a] CU1 î̂_6, 24""' ! act(• "il

Kesunar.ro parameters BN1.- •-. S

!'? ab ' Vih

1

!.i

No cross section dataava11 able.

Renonna1 îzed

Renormalîzed

Au std.

L p i t h e r m a ! r a t i o , u . l

F . p i t h f r m a l r a t i o , 0 . ^

A i s t d .

R e s o l v e d re-^ . , i<n-<-j

1 1 8 b C eV : m a x . c T t

f ro tn 1^6 5 <•'.' ( b i ' )

Page 26: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

34-Se-82

1. Pomerance PR 88, 412 (52)

2. Mannhart, Vonach ZP 210,13 (6B)

Resonance parameters BNL-32 5

RECOMMENDED

35-Br-81

1. Seren et al PR 7_7, 888 (471

2. Reynolds PR T^L, 7B1* (SO)

3. Lyon NSE 8, 378 (60) '•

4. Emery JINC 2J_, 903 (65)

5. Ricabaaa et al CJP 4_b 247!(68)

METHOD

p l ï e o s c

rtCt

act

Tnass spec

act

act

art

THER

SYMfl.

oq •

U 'ab

g!

A

C

MAI.

VALUE

2.1 • i . 5

Û.O4 5 • 0.00 5

'J. -i • : .02

'J.U4 5

-'.2 • ...4

1 . ?

,.1

RESONANCE

SYMB.

'ab

i . > HI (IT.- I)

VALUE

o.ue- '-.u-i

U . U 1

U.04

4 i . i • !

HAT IO

Resonance parameters BNL-3J'

RECOMMENDED

3 5 - B r - 9 2 m ( f c . 2 m , I T ,

I 'at

He&olVL-d r e s . .2bbb' t'V r a j .from 6S81' ( t ' «

Renoraia 1 l z e d

Kt:l. t o Br-7UJ assuir.ing- c i B r ) - a b

K c d (Co) - l U ( r . T / T o 0 . 0 5 )

Au s t d .

Resolved res., 100 to205 eV; max. co.ntrib,from 100 eV lfc.0%)

I from res. par., g:from ratio of ref. 5.The 3% of Br-82m that^-decays to Kr-82 l.reatedas negligible.

ro

Not included in F1SSPROD

Page 27: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

1 .

2 .

3 .

REFERENCE

35-Br-82 ( 3 5 . 3 h r )

3b-Kr-b2

Macnamara, Thode PR 8 0 ,

Ruby, El lefson, NSE 2±,

Kondaiah et al NP A120,

1 U

.'29

Resonance p a r a m e t e r s BNL-J2S

RECOHMLSSED

( W)

( h i )

(69)

METHÛ;.

mass 3 p* • c

a r t

a c t

ÏYMH

at

c

• l i t . )ac

• (m)ac

.at

THl

;

I

M

i U

1 '

VA1.UI

( 1 . 0 )

4 '> • 1 5

i l

. u - 3 .

. J - 1 .

i

1

RE-iONAivCE

?YMB.

' a t

d b - ' i n r

V/iLUE

! « • • • 2 ' J

U

1<IIJ

1

t --

RATIOF

- - J

VAL'JE

i

it -i

NO

Mn

O n e

COMMENTS

cross sectionaval labl tf

std.

resolved res.

data

at 40 eV

* E q u a l s 1 ower 1 un 11 from r e f . Î ^ss»jroinq e p l thurma ! . - f c r t r i i ' . t r j n >i r< L ( NR.\ i r r a d ! -rind .jpf,*-r l i m i t n i r»-f . 3 assominq

3fe-Kr-B3m ( l . B h h r , IT 1 !_•/•'

1. Macnamar^, Thode PK y - .

2. Kennet- t , Tl-.^df JINC ^ , 2CJ! I r>l !

. i r amo t I T S HN . - • ^

- . - - i

mass spec .• •. v - 1 u

I ;ah |

Not inc luded in FISSPROD

Two rp«o]ved r e s . a t 28a.id 233 eV: niax. c o n t r i b .from 28 oV ('-<"•)

K)

I .

11 . i r i ' . s f : • . • £ • ; . 1 ^ n ' î *! i r. *; R.\ . A s ? un i r: •- x T i ,. - .-* r. '.̂ I 2-JÏ t .

Page 28: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

1.

2.

1.

1.

REFERENCE

36-KT-B4

Macnainara, Thode PR 80, 2yt> ( 5u)

Kondaiah et al NP A120, 329 (68)

Resonance parameters HKL-3J5 (b>J)

RECOMMENDED

36-Kr-d5m (4.4 hrs: IT 23*)

3b-Kr-B5 (10.76 yr)

Macnamara, Thode PR j30, 296 (50)

RECOMMENDED

36-Kr-Sb

Macnamara, Thode PR J30, 296 (50)

Resonance parameters BNL-325 (60)

RECOMMENDED

METHOD

mass spec

act

mass spec

mass spec

THERMAL

SYMB.

r

c

ac

~ ah

g°iE"

c

A

ab

0.

0

c

VALUS

uyû- û.'jl J

.0B-I.'.'J2

0 . 0 "

0 . ij j

<15

6

«•2

• 0

1

RESOUAliCt:

SVHB.

ab-jnr

\ ^

^ab

^ab

VALU h

J . 1 t 0

•3. J

. _ — —

2

-.0

0

XATlu.

| KYKB. V/U-l t

— T ;

i

C'JMMtMT;;

Two r«6oi"ed res. at Sly

and 580 eVr max. contrib.

£rora 519 eV (157)

It is assumed that

•im)/-(^) • U

Not xncluded in flSSPROL»

No resonances assigned tothis isotope

I

ro

Page 29: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

37-Rb-85

1. Seren et al PR 7_2. 8 8 a (47)

2. Lyon NSE 8, 378 (60)

3. Keisch PR JJÎ9, 769 (63)

4. "ira, Bettonl En Nucleare 14.228 (67)

5. Suns, Juhnke JINC 29_, 2853 (67|

6. Ricabarra et al CJP 4_\ 2031 (f>9)

Resonance parameters BN1.-32 5

RECOMMENDED

J7-Rb-Bb (18.7 d)

j7-Rb-B7 (5 x 1.' ,r)

i. . Serer. et al ?H 7_2 , 8H8 (47)

Resonance parameters EiNL-i2!:

RECCMMENUE-

METHuD

act

act

act

act

,ct

act

acr

THERMAL

SYMB.

ac

" ac

'^ ac

Ac

5'ac

at'

-

"'al.

ar:

at

......rtb. ;

VALUE

0.7.J.14

1 .0

0.51 -0.04

0.45rO.04

U . 34(-J : 0. I:J5

•. .14-0.,.,2

'.42

1• 1 ;

i

- . 1 * • . .•'>

• . i i " . '•

i

RESONANCE

SYMB.

1ac

T

"ab

ab-unr

'ab

VALUE

24,7:1.7

2 . 5 Kl. )

0 . 07

_ 1 _

I

.it;- inr

Iat.

[

i

RATIOS

SYMB .

i.V

VALUE

1 b . 3 • 0 . 5

COMMENTS

Renormalized

RcatCo^lCr.-TA.-O.OS)

Co std.

Au std.

Resolved res,, 176 to6900 eV: max. contrib.from 528 eV 15 5%)

No cross section dat*iaval 1able

Resolved res., 267 toB55O eV- max. contrib.from 378 eV (HOs..)

ai

I

Page 30: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

3B-sr-8t<

1. Seren et al PR 72, 880 (47)

2. Lyon et al NSE 8, 378 (60)

3. Hans et al NP j!0, 183 (60)

4. Kramer, Wahl NSE 2^, 376 (65)

5. Para, Bettoni En. Nucleare 14,228 (67)

6. Mannhart, Vonach ZP 210, 13 (66)

Resonance parameters

RECOMMENDED

38-5r-87m

(2.83 hr; IT 99.3%: EC 0.7%)

38-Sr-87

Resonance parameters BI1L-325

RECOMMENDED

METHOD

act

act

act

act

act

act.

!

THERMAL

SYMB.

y • ( m )ac

'' (m)ac

g°(mlac

•3°(ro)ac

g°(m)ac

g°(m)ac

9'ab

*ab

VALUE

1.3-0.25

1.73

0.8=0.25

I . U I O . 1

0.94:0.05

0.81=0.04

0.6=0.1

i.O

10.7 rl.4

4.)

RESONANCE

SYMB.

Jab

ab-unr

aab '

ab-unr

Xab

t

VALUE

2.7T0.b

0.24

3.0

S>8 ! 1 3

0.5

iOÛ

RATIOS |

SYMB.

I/y-

VALUE

13.J)

1

Renorraali ̂ sd

Rcd(co) = l'J(r. T/To_-0.05)

An std.Rcd(Au)-3.6lr T/T^-0.021)I/g° from R^d(Se-86)

Resolved res., 590 to4480 eV; max. contrib.from 590 eV <t35%)

It is assumed that ?(g)/^(m) ^0.1 and that allSr-87m decays by IT.(FISSPROD cannot deal withelectron conversion)

Not included in FISSPROD

Resolved res., 3.56 to3700 eV- max. contrib.from 3.5b eV [97%).

I

to

Page 31: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

HEFKRiNi.t METHOD

j B - i r - r i e

ï . S e r e n e t a l PB 7 ; , 88S ( 4 " :

2 . Roy e t .il CJC j j _ . " J i d m-il s o Plv - : l t . . 14 ( SMi

R e s o n a n c e p a r a n u - t e r s bNL- ••*:>

RENOMMENT£D

? 8 - E r - a - i (=>:> d )

L . E a s t w o o d e t a i P I C - 2 i t> , 5-4 (~-~i)

RECOMMENCER

i . , ' e i « e ; Act i P h y s Avist £_î . 2 . '

RECOMMENDF.:i

i b - S r - J l ( • ) . ' . " hr<

I

act

l e t

THE HAM.

s •«'M a .

a ^

J!-

c

ac

• -

. 1

1

a l

a b

( 4 . S 1 . 1 ) l ' j -

• " , . £ ) • • . • . • • ) 1 0 "

•.' . J U T

•J. 4 J • C. 04

J . 4 2

- . H • ' ' . j

j . n

KESON/vNCE

S VMM.

J ab

ab-;.jnr

: a b

VALUE

\

0 . Citj t 0 . 0 i

<0.01

U . 0<i

RATIOS

.-YHh.

"

- - - - I

VALUE

_. . _

COMMEÎv'TS

Reso lved r e s . , 2780 t o2 3800 eV; ma>.. c o n t n h ,from 2 7 80 eV (faS%)

S u p e r s e d e s CJP _3_5 • 1215(57)

No c r o s E sec t ; -vi d.ita •

I

Page 32: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

;u.n.k>r.,L

.t l - ï i l i

; . H o ' h e / . . N.i? t . : , . • i 4i >

r . e r e n e l >1 IK J , n - n ( •; ' i

J . H a m s e t i l PK 21' • 1 ; ( ' - ' I

4 . P o m e r a n c ? 1'K b_] , t ,41 I j l i

b. B e n o i s t e t a l J i 'K ij , \rt-i 1 'i 1 )

6 . ( i u s t a d f t i l [ A - O - G E N - ~J-2ti.

0 4 ( i > 4 )

Resonance parameters BN'L-iJ^

RECO.<MENDED

3 9 - Y - y O ( b 4 . 0 h r !

I . S m i t h , B o e d e r .TCP 23^, 2 1 0 8 ( S ' j )

RECOMMENDED

3 9 - Y - y l ( i B . B d )

1. Milton, Grumraitt CJP iti, Ibyj

it'))

RECOMMENDED

Ml i l l .

• '

' '

i . - l

L l l l . - . - , .

P . I . ' - .< •

t '-t t

a c t

, , t

: Hi

:

' .11.

i t

il..

f ' . , b

ri '

etc

V

11 . at 1 .

r ' . .• j r n i d i i . ' i •<!

Au : j td .

Ht-soived res. , Ih'j47r,o t-V; max. .-'.jritfiorn 1'bOC eV (4rj,v)

to00

Page 33: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 29 -

IL <nt . E - E -

V, G

a: r~-

-r

Page 34: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFEKLNCt. i l! KM/il .

L. i M - . I VAJLiJi.

1, Pomerance pp

RECOMMENDED

4 O - Z r - 4 J ( 1 . 5 x 1 0 ' y r )

i . B N L - Î 2 3 ( 5 H )

Resonance parameters BNL-12S\ 5b )

RECOMMENDED

49-Zr-44

1 . i e r e n e t a l PR 2 1 . B b t l ( 4 ~ J

2 . Pomerance PK t)B, 412 Î52)

3. Lyon NSE 8 , 378 (601

R e s o n a n c e p a r a m e t e r s BNL-325

RECOMMENDED

I

j

a;

a b

a c t

p i l e o s c

a c t

. ._ J

•~.c

a t

- •>

U . 4 . , . 2

0 . 0 8 , 0 . 0 4

0 . 0 7 5

U . O 2

0 . 07

• 1

I

, • ; 1 • • ;

J . 11

^ b

1ab

ab-unr

2 2

0 . 2 0 - O . I S

0 . JO

II. 2b

\ - . . , : . . . .

T.p-J i . "-'.•'I. 'UV il

. _ . . . .

ifpuLl . J;-...L data. .Singleresonance -it 1 I u uV .

r • - • - -

u r i n a l J S S i , n m , , , . , r - 9 2

1 J C o | 1 0 ( r T / T , =0.05)od

R e s o l v e d r e s . , 22bO t o710U eV: max. c n n t r i b .troxn . '2bJ eV ( 7 '_>•» )

o

Page 35: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 29 -

î2 §

Page 36: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

RilFERENCL

1. Pome r i n ce f'H tUi , 41J

ResuridiiOf p a r a m e t e r s

L I HKSUNA »

VALL'K ! SYMU. ! ' .ALU..

RECOMMENDED

40-Zr-93 (1.5 x 10* yr)

1. BNL.-325 (58)

Resonance parameters BNL-32 5(58)

.. i • ; • u . 11 j

i , : >. 1 1ab-unr I

.BH!i i-V; ir,iy. cu'.ti

- t u - ; 1 " ' ' •.' ( ;•..-...)

ab

I, Unpubl . jlv.;L data. Single! resonance at 110 eV.

RECOMMENDED 22

40-Zr-94

1. Seren et al PR 7_2. 8 B B

2. Pomerance PR 88, 412 ;52!

3. Lyon NSE B, 378 (6C/)

Resonance parameters DKL-325

pile osc | y -

f0 . 4 J I ). 2

'J. 08.0.04

0.07'j

U.02ab

ab-unr

0.2O0.ÙM

IO.Lib !

Original asslynni(-'nt /.r-92

(Cn)=10(r V/To =0.U5)H (

Resolved res., 2260 to7100 eV: max. contrib.from ?2bJ eV ( 7 b*)

O

RECOMMENDED 0.07ab

0.2b '

Page 37: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

RLFEKENOE

4 O.-_Xr - 1^

1 . j e r i T , - t i l PH •_*, rid ri .

2 . ~ < n y / i r . Go 1 J h a ^ e r PH _ ^ ,

) . P o r a e r r t n c e P r 8 d . 4 1 J I S 2

i . L y o n NsE d , • ' -* ( t '

Hti'OM.HESi'1 I1

4 - . ' r - i t . ' . . :. t

MF. TU', i

THF PMA.1

V M M . VAIXF.

. 1 • J . 1

HE.SON

VMH.

! - .Mr

1

1 • • - • • *

1

RATIO?

SVMB.

i

VALUfc

4

i

COMMENTS

Uu cross sectiun dataaval1abie

Origmal assi jrunent Zr-44

H r d(Co) -iCîr T 'I o- J. >:•:,)

Resolved res., iuo tur»970 eV- m.ix, ronLrxb.from 300 i-V (Hb%)

N ! cross sect . • T d it ai V .̂ 1 1 11 • 1 C

N • T 5 F Sf T . ' i (• j

•IV U i 11 it'

I

Page 38: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

4 2-1^0-^5

1. Pomeranco PH. dB, 412 (52)

2. T a t t e r s a l l e t a l JNE Al 2 ,32 (b'j)

Resonance p a r a m e t e r s BHL-125

RECOMMENDED

42-MO-96

1. Pomerance PR 88, 412 (52)

Resonance parameters BNL-32 5

RECOMMENDED

42-MO-97

1, Pomerance PR 8 8 , 412 (52)

Resonance p a r a m e t e r s BNL-325

RECOMMENDED

MKTHUD

p i l e •-!s<•

p i l e o s c

pi le osc

p i l e osc

TH

SYMb.

I.tl

- a .

" at

- a h

ah

- , b

IO!Ai

VAl.lil.

1 ' . I • 1 . i

>. 1 • . ri

1 4 . ' .

u . 9 • U . 2

1 . 2

2 . 2 - 0 . 7

0 . i

2 . 2

HE.S11N

SYMB.

' . b

I

,\U- . j n r

l a b

d b - a n r

\ , b

ab-unr

VALUK

1 '_• 1J - 2>i

•J 7 ; 1 5

4

10U

0 . 4

2 5

1 1 : 3

4

1 5

RAT

: VMH.

lo;>

VAX.UKCOMMtlJT:

Au s t d .

Harwell B and Au s t d .

Resolved r e s . , 45 to 900 eVMax. L-ontnL. from 45 eV

Au s t d .

Resolved r e s . , 113 t o3280 eVr max. c o n t r i b .from 131 ev (98%)

Au s t d .

Resolved r e s . , 7 1 to 7 8beV: max. contr i l ) from71 tV (63%)

I

Page 39: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

i .

2

3 .

4 .

• > .

h .

7 .

à.

REFERENCE

42-Mo-':)8

Seren e t a l

Pomerance PR

Dahlberq f t

Lyon NSE 8,

Cabel l JIHC

Kachiqashev,

PR 7.2, 6H3 (4")

aij , 41J 1 rj2;

a l J N E J _ £ , S i ( t j C I

3 7 8 ( 6 0 )

£ i , 1 ( 6 1 )

P o p o v AE J _ 5 , 1 2 0( 6 i j

Baumann I;p-dl7 ( t, J )

S Lins , J inr>.e

Res on a n j e L -3

JINC i^, 2H5 '. (• ' i

r w i c t e r s BNL- -i.' '••

ME

a

P i i

a

a

a

THt

,-r

et .

e t

e t

: t r

: t

- t

niERHAJ.

5VMB.

I ' i •

y m.- Th 1t r

ri ':

.- r i ^ ̂ ^*?rt : ' t i l

sr-11 '. • • r t. ; i !

l I A i . A . F - i r i s .

AL'JE SVMB. I VAl.:;i

I .SH

HESONAIXE K.VT1-.V

SVMB .

"' . l 0 •

i l - • • i :

I î

VALL'i.

14'il

COHMhNT.-

A .i b t Ci .

, , J s t d .

KfjiCoi = li. i r T T ,

AJ s td.

AJ std.

.'o s td.

Hi s u l v - f d r .-•- . . 1 «i K't. i'V- n i- . .- ir.tt r uni 4» t • i 4 \ !

[ • i s : . i : t

UJ

Page 40: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

1.

2.

3.

4.

5.

6.

7.

REFERENCE

42-MO-99 (67 hr, B7% tuTC-9λ)

42-MO-100

Seren et al PR 12^, 888 (47)

Sui.yar, Goldhaber PR lb_, 139(49)

Pomerance PR 88, 412 (52)

Cabell JNE A12. 172 (60)

Kachigaahev, Popov AE 15, 120<b3)

Baumann DP-817 (63)

Ricabarra et al CJP £7, 2031 (69

Resonance parameters BNL-32 5

RECOMMENDED

METHOD

act

act

pile osc

act

spectr

net

act

SYMJB

aL

ac

ab

- a b

THERMAL

' 1

| VALUL

RKS'JNAi;ci:

' t:ïMB.

1 ' * '

U . 4 -j : U . ) ̂

0 ', • 'j . -,

•J. I')-)- L ' . •.••.••

0 . Î • 0 . 1

U . <! 0

KIJC

VAi

<

R! i.B4ac

j

I •. .b

I . 1ab-unr

Ml.

1U

• U . 2 • •

-2.3

HAT 1US

JïMB .

I r

1 M -

I-/

VAL;.t

1lM.ri)

i1 ! *. ti - '^ . b

IB. : ;.7

COMMENTS

No cross section dataa . a i - J 1:1 ' •

Kencrmali/ed

Au std.

Au std. ( . ] % res.5el£'-shleldinq)

Au std.

Resolved res., 97 to1670 eV: max. contrib.from 364 eV (84%)

I

0J

NOTE. The uncertainty m '" ' noted for Mo-98 also applies here, except that the effect on Ia^ °^ halving . wojld be greater(-- 40%). The B filter measurements reported in ref. fa indicate the possible presence o£ a higher er.<-r̂ / resonance makinga significant, contribution to I a b.

Page 41: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

1.

2 .

3 .

1 .

REFERENCE

43-Tc-99m ( 6 . 0 h r

43-TC-99 (2.1X.106

Pomerance ORNL-19~7 5,

Pattenden PIC-2 L±,

Tattersall et al JNE

Resonance parameters

RECOMMENDED

44-Ru-lOù

Halper in e t a l ORNL -

Resonance par amener s

, IT 100%)

M

31 ( -in )

44 (58)

A l i . 32(60)

BNL-325

j 3 J i , 4

BKL- • : 5

METHUD

p i l e i, s e

cr/s spe-

p 1. 11- ûSf

mass s pe j

SïMB.

a ;

""a .

a t

" ' a :

• • - \ :

RECOMHfc:NDEJ

H i ' . p c n r . ••• i l . ' R M . - ' f ' U , 4

H--sor. <:.^i- ; . i i . r . e t e r s BHL-.1»

Hi i/ JMMFN-F:

i RAI iu.~COMMENTS

No cross sert ion dataavaa1able

Au s t d .

Harwell B and Au s t d .

Resolved r e s . , 5.b to195 eV- max. c u n t r i b .from 5.6 eV (Btnj

No rosundiici's a s s i <

to tr. i s i soi ope

4 •>.. *.'V • m Ù . X . -'v •!. î i

Page 42: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

1 .

2 .

3 .

4 .

1 .

2 .

3 .

1 .

REFERENCE

44-RU-1U2

Seren e t a l PR T_2, 888 (47)

Ka tco f f , Vvilliams JINC 7 , 194..(58)

Lai-.tz ORNL-3832, 6 (65)

R i c a b a r r a e t a l CJP 42., 2031 (b9 ,

Resonance parameters BNL-32C

RECOMMENDED

4 4 - R U - 1 0 3 ( 3 9 . 6 d )

44-RU-104

Seren e t al PR 72, 888 (47)

Sunyar, Goldhaber PR 76, 189(49)

Lantz, ORNL-3679, 11 (64)

Resonance parameters BNL-32 5

RECOMMENDED

4 4 - R U - 1 0 5 ( 4 . 4 4 h r )

S h a r m a Nuo Ciir, 1 7 , 637 ( 6 0 )

RECOMMENDEDj

METHOD

a c t

ac-t

a c t

a c t

a c t

act

a c t

a c t

•;

SYMB.

A

ar

*V

ab

*\»

"'ab

A

ac

"*ab

9 ab

HERMAN

VAl.Lt

1 . - i

• ) . 1 4 • 0 . •. 1

1 i

( 5 )

0 . 7 • J . 4

0 . 4 7

'J

ij. A •

„ . 3 J . •_

U. J J

KElaO-NANL't

SYMB.

1

HI

^ b

1 ,dh-unr

HI

R I ac

Iac

VALUE

4 . 7 - . . ;

4 . 14

^ ' . 4 - 0 , 4

\

T ^

; 'lu

u

4 . 4

-4-

HAT I L>:

h-ïMIi. VA1.LK

r - - • y

i . i '

1. j '

i i . l ;

O . 4 ,

i

CJMMLNTS

H e n o r m a l i z e o

1 i C d e d u c e d trorti q u o t e dCcl d i t t .

Aa s t d .

One resolved res, at2 00 eV

No cross section dataavailable

Renormalxzed

Nc resonances assujnedto this isotope

D o a b l o c a p t . . ru î i i K -

Hunormalized to

Page 43: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

44-RU-106 (1.0 yr)

1. Werner, Eastwood NSL 2_1, 20(65)

THEHMAL

VALVE

HE:;ONAA"CECOMMENTS

RECOMMENDED'• I

45-Rh-lG3

1. Seren et al PR 22 > 8 8 8 (47 1

2. Harris et al PR 7_9. H (5°l

i. Harris et al PR dû, Î42 (50)

4 . P o m e r a n c e PR BJ. 6 4 1 ( 5 1 )

5 . C u m m i n s AERE R/R 2 3 3 3 ( S O

b . R o s e e t a l P I C - 2 l_o , 34 (St>>

F u i t e t a , ( J t o m o JA.F.R 1 - i Oi ') i h

M. W a l k e r , C o p l P . ' <VP •'4 14H' .(r, ;

p i ± e os /

p i Lc nsi-

p i l e J S :

p i l e L. s -

P i I..- OB

3 . 1

!

Renorraal ued

Corrected for resonanceself-shîeldinq

B std.

Au std.

Harwell a std.

Harwell B std.

In std.

R e s o l v e d r e s . . 1 .2b t e442 L*V • max. j o r . t r ir .from 1 . 2*-. .-V ( aH> i

L se wj th Wtstro'.' .i-va l J f ï I J C J ' I I 1 . . .

Page 44: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

1 .

• l ' j - K h - 1 •'. ( )'i Mr

-.-t .i 1 j INC ^ , 1 .'

11.2 i

^ . G le f ï c i t - n i l i e t .» 1 HAP:> V*. I ' I i t 4 i

J . G l e n d e m r . S c n m i t t NSL ^ _ j , > i d

(b-1 I

4 . Ha i p e r m >;t a ! URNL-i ' l ' 4 , .' (••

5. Gler.denl. , Srittin NSE Jj», i;.

RECOMMENDED

Resonance parameters BNL-i^-

RECOMMfNDhD

4a-pd-;JS

Resonance parameters BNI.-'.?r-

RECOMMENDED

46-Pd-Mfa

1. Lant; s-t al uHNL-Ji.-74, iv (•••;.

Resonance parameters BNL-l*'i

j ̂ «• •- ;J>-

P.ECUMMENI't::

f• M l - .

(!• " i - l

No resonances dssiyned to

this isotope

I

-i-

t 1 . i

Kesolved res., 12 :o '.S2

eVr max. contrib. frcin

1 j . 2 oV (4 33 )

One resolved res. at

5J(; eV

'-.L. ̂ , -i 1

œ

Page 45: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCETHtRMAl.

METHUL-

1. ; t r e c • " .1 F h /_-

Me i s t i t . ' V i t . r f

' . .-«.-rv-jal e t a l Si ^

•> . L /o r . N^F H , • '", i

I 4 ~

a!

9

j

-i '

VALU

1 • !

: : . • • .

; - . • - .

h. SYMB. I VALUE„

K C C J I C O ) - I 0 | r T T . . . i ' (.".>)

K > • b . • i ',. t. d r • s . ' .

• * * e V • n w t x . ^»r i t - r

t r om ' ' *'V

Page 46: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

iI_--ÎNJ. ' 'J- '

1. : i-ron e t .il PR y , HUH { •! "" l

: ' . H a r r i s e t i l PR 7_y • 1 ' ( • • ' !

ï . romerdii..-< PR HB, 4 1 . r i . . ' )

4 . - e h . ( a l 1 v . i . . , ' . P h y s . i_l h K ; ( '

'>. I j t ' . i - r s a l i i-t a l JKl A_l̂ I.'

' h'.

t , . Lyon NSE 8 , J"rt l t ,O)

7 . K f i s r h PK 1 _ ^ , >.4 t - * i

9 . B r e s e s t l Pî .il JIN«." J^ . -'•> "

Simn, JuhnKf JINC <•:. (4 ' '

pi 1.

RECOMMENDED

1i l

• ( m l

I ° i m I

•4 . " H • • ! . 4 7

a b

ilj-unr

I , Ira!ab

1400- iL

1 •

I < i r . ) . ' ' j ( m )

I (m I.

1 •'.. 1 • u . 4

OMM) N'IS

' ' ; r r r i ' t c d li.-i

A. s t d .

H'irv/eil fl ami Au s t d s .

R c d l C o ) l O i r T , T r . WJ.O'i

Au s t d .

Pcsolved r e s . , b.2 to5CJ5 eV; max. c o n t r i b .from '3.2 eV |9 5?.l

oI

Page 47: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

1 .

1.

REFERENCE

«'7-Ag-ilJm C M

H a r t . Graham C.IP 41

RECOMMKNDED

4 " - A q - : 1 1 ( - . •„• d

Dr- , • .-1 , H. i l p e r : : .

RECOMMENCED

B a . jo- k -if. * 1 .RM!

— n,r.-, M — r

4h -Cd :_. ._.

P . , 1 • .- ' . . UN1.

d, IT i . U'-

, i i 2 1 ( f, 1 i

••RKL- V"4-; ,

7 ; M. 1

* B S I - *?'<

M E T H O D

l e t

- , = - • - . -

SYMB .

' a i .

ï "

a "

• :

-3 .

THERMAL

VALLTE

3

1 ! • ]

'• . 4 - . 3

i

i

RESONANCE

SYKfl.

HIac

1 ,. . , : ,

I ,i!

1

' '

' . '

VfXLE

1 • " " - -

; :i

i l •(

't -1

RATIOS

S'i'MP. VALUE

— Co

i n p

Peso

.' !•]

! r ! m

CUHMENTP

std.

res ilwd ra. at HO eV

1 ved r e s . . .' ' . ' t oe V • max . . on 1 i i i i .

< -' . " O V '• >. -•

Page 48: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

4B-C3-U2

1. Baldock. et jl ORNL-1494 t 1! hbj

Resonance par^mf:ers BNL-32 5

RECOMMENDED

METHOD

mass spec

THERMAL

SYMH.

A

c

""~ab

^ . b

VALUE

.'. J •;).")

(J . 1 :j • 1. . .j

KESONANCE

SYMB.

'al,

.ib- unr

VALUE

J::

1 J

.SVMll. VAi.L't.

J Two resolved res. ,.it b7J jnd 22 7 eV : max. c o n t n b ,i from t.7 eV lbtJ%)

48-Cd-j.l 3

BNL- 325 (66) data is used for the 2200 m/s cross sect ion ot Cd, e>i-cpt that h A - t < - - - v i; .-t

of Meadows and Whalen, obtaining " (Cd) = 2484 b INSE i.1 , 1 *.2 ( b B ) / . The valt.t- re.-cinun«-ad("1 t^r <'d-ll • .s3D

b a s e d o n ' , (Cd) - 2 4 4 5 b , a s s u m i n g n o s i g n i f i c a n t c o n t r i b u t i o n frunv o t h . - r i s o t o p e s a i . J i i . a t j r a l d b i r . d i n i < j

a u

for Cd-llJ of 12.26*.

t<0

I

RECOMMSNDED Use with Westcott g ands values (AECL-LlOi)

Page 49: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

4B-Cd-114

1. Seren et al PR 21. 888 (47)

2. Pearlstein, Miliigan NSE 2b^,281 (66)

Resonance parameters BNL-325

RECOMMENDED

48-Cd-l15ro 143 :1 , no IT)

4S-i_-â-ll 7J (2.2) d)

4_a-ca-iit

i 5-eren et \1 S'P "*. d8.H 4" (

- .: /ar . C»-.ir \:?r [lH " ' . 1H -)

« v M . . . . . ••' •• . •;-

: - *• . !:• .y. . T . r , J. - • .\ • .

MF.THOD

act

act

i rt

-

THERMAL

SYMB.

(TT)ac

" ab

'3?aÇ'

.-'là-âC 1

VALUE

U . 14 i 0 . 0 3

1 . ' • 0 . 2

0. C 3fcrÛ.0i.'7

:.3uCiO.O15

J . i •• i C . u 5

. -4

.3-'

a ; '

1 •: s »

i

i ' •P" - :i

. "7- . . .'•

RESONANCE

SYMB.

KII.J)

Xab

ab-jnr

VALUE

2 1. 3 r ? . 0

9.6;2.b

b.2

I ,(m) j 3îb !

:

1i i

i

H l l ir l • i C

' i:

RATIOS

SYMB. VALUE

1

|

i

COMMENTS

Renormalized

One resolved res. at 120

eV

No cross section data

available

Nu cross sect i or. d^t A

,*va I i able

Renuraa}ired

N ri'3:«!,ir.:es i > s ; ;:•• :ï

t • h ; p i «s J '- . : -r •

I

• t - - -

Page 50: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

49~In-115

(Absorption by Naturally-Occurring In)

1. Pomerance PR E53_, 641 (51)

2. Cunanins, Spurway AERE R/M-100 (57)

3. Tattersall et al JNE Al2,3C 160)

4. Fuketa, Otomo JAERI-1009(60)

5. Meadows, Whalen NSE Q, 132(61)

6. Scoville et al TANS b, 373(62)

7. Huttel, Liewers Kernenergie 6,336 (63)

8. Vidai CEA-R2486 (64)

Weighted mean ofmeasurements

Contribution ofIn-115

Resonance parameters BNL-325

RECOMMENDED

HETHOD

pile esc

pile -sc

pile osc

pale osc

pulsed n

react.

pile osc

pile osc

THERMAL

SYMB. 1 VALUE

1

3"ab

^ a b

g'ab

g"ab

g 9ab

g°ab

l'2ab

g 5ab .

lyyiio

147 T 3

UJb. 2

190-=7

ly8:2

198.3.1.1

i yv.s.o.y

205.H.1.0

205.6:b

2 06

RESONANCE

SYMB.

R Iab

^ b

^ b

ab-unr

Xab

VALUE

3600.35U

3300.B50

3140.70

J21Oil7O

3340.170

3170.60

20

3340

R/vTIUS

SYMB. VALL'E COMMENTS

Au std.

Harwell B std.

Harwell B and Au stds.

B std. Reported "ab; g =1.017 assumed.

Assuming, for ln-113.nat.ahund.=4.28%, q° .=11 b..I a b . 270 b. a b

Assuming g-1.017. Resolvedres. , 1.46 to 95 eV, max.contrib. from 1.46 eVl97%)

Use with Westcott g factor

Page 51: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE METHODTHERMAL

VALUE

RESONANCE

SYMB. VALUE SYMB. VALUECOMMENTS

4 9 - I n - 1 1 5 (ACTIVATION of 54ni

1. Seren e t a i PR 2 1 . 8 a B f47)

2 . H a r r i s e t a l PR 2 1 , 11 (50)

3. S e h g a l I n d . J . P h y s . 2 1 . 6 3 0 > 5 7 !

4 . M y a s i B h c h e v a e t a i JNE b, 2 3 C I 5 7 I

5 . h e i s t e r Z . N a t u r f 1 3 a , 6 2 0 ( 5 8 )

6 . W a l k e r e t a l C J P j 8 , 57 ( 6 0 )

7 . Jaclts D F - 6 0 8 ( 6 1 )

8 . Brown e t a i TANS l % J 7 t (62)

9. W a l k e r , J a r v i s AECL-1625 !fc2)

10. Becfcj r ts e t a l SSE 12, 32e) i h !

1 1 . j u ; e ! o w i c 2 Nukltor .xka 8 , 4 i7 t ]

12. Bauraann DP-B17 \ftt•

13 . St av l ssK l l , 5!;erman Suv. A.E 19 ,1 2 C ( 6 5 i

Weighted Mean

act

act

art

act

act

144.-14

ni» ID

1-2, IV:

S" .h-r4 .4

259S

RenorTnalized

I /q : 15.2

.j^l.4 i U s m q quoted R c j -

! Au Std.

Au std; corrected for non1 w" I 17.3=1.0 1/E spectrum.

I 1 6 . 7 : 0 . 7 ! A J a t d .

I j -

Rl J °

.J ! AJ s td .! **

. 4 ^ | R e p o r t e d ' a c - g = 1 . 0 1 ?' a s s j m e d .

Mn std. q a c quoted, g-Î.ÙJi

t 3BS Jired

1 -)* i 1 6 . 7 - 3 . 5 Au s t d .

Page 52: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

THERMAL RESONANCE RATIOS

METHODSYMB. VALUE

5O-Sn-116

Resonance parameters BNL-32 5 J ab 0. 24;0.08

SYMB. VALUE SYMB. ; VALUii

ab-unr

li.Brl.

COMMENTS

Resolved res., Ill to3400 eV; max. contrib.from 111 eV (90%)

RECOMMENDED •3'ab 'ab I 1 5

50-Sn-117

Resonance parameters BNL-32 5 - ab C.15rO.O5

ab-unr

I 9.5,0.9

2.5

Resolved ies., 1.3 to995 eV; iax. contrib.from 38.8 eV (38%!

RECOMMENDED 9'ab (i.4)» ab 12

50-Sn-lia

1. Seren et al, PR 21. 888 (47)

2. Mihelich, Hill PR 72, 74J (50)

Resonance parameters BNL-325

act.

act.

"»»

-'ah

.05i.01

0.01

:•. llrO.04- 'ab

ab-unr

Renormaiized

Rencrmalized to T.= 250 d

Resolved res., 45.8 to770 eV; max. coutrib.from 4 5.8 eV (30%)

RECOMMENDED g- a b(m) • 0.02

( 0 . 8 ) '

0 . 2

50-Sn-119i3 ( 2 5 0 d; I T , 100%) ab (5.0)

50-Sn-119

Resonance parameters BNL-325 - ab 0.0 3t0.01 2.1:0.

1.4

No cross section dataav aliable

Resolved res. , 6.2 tc.948 eV: max. contrib,from 223_eV [20%l

RECOMMENDED (1.2)' 3.5

* Thermal cross sections for Sn'1" and Sn1'" are based on an assumed valae of 40 for the cross section ratio for the formation of low and high

spin isomers, ~\/2''\i/2 anc* ' 3/2/ "ll/1 .based on available data for Cci, Sn and Te îsomeric cross sections. Assuming also a cross section of

about lb for Sn 1'*, the contribution to " e l e m ' ~O b 3 l'' £ r o m a 1 1 even Si; isotopes is 0.3Ï fc. The capture ,-ray yields of Groshev et al. JNE

A12, 57 (60! indicate that the three odd A isotopes make nearly equal contributions to "ejej-- Th-is a— • 5 L . -, - J L , °,is -- i(.63b-.33b) . .1 b.On the basis of calculated values of all g- 1.

Page 53: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

50-Sn-lJO

1. Seren et al PR _7_2, 888 (47/

Resonance parameters BNL-32 5

RECOMMENDED

50-Sn-lJlm (76 yr)

5O-Sn-121 (27 hr)

50-.Sr.-l22

1. Seren et al PR 7_2, 888 (47)

2. S-ir./ar, Goldhaber. PR 7_6. !99 l4"*'

3. Mar.jai . îili NP 41, 372 (63!

•J. Tllbur/. Kramer SSE _U , 54 5 , tB

Resonance parameters BNL-325

RECUMMESDEr

METHOD

•et

act

act

act

act

THERMAL

SYMB.

•|g>

ac

" ab

ab

' 1 m iac

oy(m)ac

j'lm)ac

ab

ab

VALUE

<.'. 22-0. 04

0

- 0

0.2

( 50|

150)

,. -JO. 06

<>. . Jt; 0.031

;.15,'J.C2

0.18

0. 001

RESONANCE

SYMB.

rab

ab-unr

Ia c

Iab

ii

at

VALUE

O.BrO.1

0. "

1 .5

Q.55-C. jf.

- . b

RATIOS

SYMB. VALUE

,'

"(ql.-'lm-^)

. . _ L

1

1

0.0048=0.00 3 5

jCOMMENTS

Renormalîzed

Resolved res., 365 to953 eV; max. contrib.from -.27 eV ( 5 5%)

It is assumed that•(m)/ (g) < 0.1 and -(m)can be neglected.

No cross section dataavailable

No cross section dataavailable

Renormalized

A.J std.

Resolved r^s., 107 to6B50 eV : ma.-, contrib.from 107 rt'"/i 50> )

Page 54: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

1 .

2.

3 .

4 .

1REFERENCE

5O-Sn-123m ( 4 J m : n o I T l

5 0 - 3 n - 1 2 J {125 d)

59-S11-124

S e r e n e t a l PR 7_2 , 8 8 6 ( 4 7 )

S u n y a r , G o l d h a b e r PR ]_b, 1 81 ( 4 9 )

Mar.gaJ, , G U I Np 4 1 , 372 ( 6 3 )

T i l b u r y , K r a m e r NSE J U , 54 5 ( t b l

R e s o n a n c e p a r a m e t e r s BNL-32 5

RECOMMENDED

S 0 - S n - 1 2 5 m ( 9 . 7 m, no IT)

5 0 - S n - 1 2 5 ( 9 . 4 d)

5 O - S n - I 2 b ( 10" v'l

METHUO

a c t

a c t

a c t

a c t

1

SYMB.

f,

etc

a c

a c

a b

a b

a b

' a b

HER.MAL

VALUE

( id)

' J . 5 J - 0 .

• J . l - i t ' j .

O . l j 5 r O .

>j . i 3 - C .

'J.lfarO.

0. 1 3

Û.004

( 5 0 )

( 5 0 )

l . j

RESONAÎJCE

SYMfc.

* •

0 3 :

11 ac

0 1 9

Ù2

0 5

Iab- anr

'ab 1 ™'

VALUE

< 1 0

1 0 . 7 r 0 . fa

0 . 3

9

3.O3

RATIOS

SYHB.

. .J

VALUE

U. u lb t i

J

I

COMMENTS

Not im-ljded in F1JSPRCD

No cross section dataavail able

Renonnfll îzed

Henormaiîzed

Au std.

Resolved r e s . , 62 to950 eV: max. contrib.from b2 eV 199.5%)

Net included m FISSPROD

No cross section data

avai1 able

1 No cross section riata| avaliable:

œi

Page 55: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range
Page 56: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 49 -

Page 57: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range
Page 58: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

Sl -5b -121

1. Ss ren «.t a l ?R T_k, 888 (47)

2. H a t r i s e t j l PR 7_9_, 11 (50)

1. Pomeranci-' PR ̂ B , 412 152)

4. Sehqal e t al NP 1_2_, 261 (59)

5. Lyon NSE B, 37B ifaO)

6 der Hatcosian, Sehgal k>P. 125,1615 (62)

7. Rardon, Kiss KFKI Kozle 14 85

8. Crvir.i, Maxia Ener^ia NucLeare

M , 54 1 I 6 ,' j

Resunance ji

RESOHAHΠRATIOS

i act

I act

') . t • 1 . 3

S.'.'rO. 5

IJ . 1 ') r 0 . 0 i

7 . 0 î 'i . 7

5YMB.

3 I -.P •

VALUE ! SYMB.

a. - un r

VALUE

i.'-r Î4.1

(ra, ' iqi I B 3 : 9. ) 1 0 *

COMMENTS

Renormalized

C-»rrectûd for resonanceself-shielding

.VJ std.

Au s td .

P.fsolued r eE . , ^..2 t o1b 7 eV: max. con L r i b .f rciïTi 6 .1' eV ( 55'^,

RECOMMENDED I 2-

f Not inc luded ir: f-"î Sîr'

Page 59: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

I .

2 .

3

• I .

S.

6 .

7 .

U.

REFERENCE

51-Sb-122 12.80 d ; EC, 3'X)

dor Mateos i an e t a l PR 7_2, 1271( 4 7 )

S e i e r . e t a l PS J72_> B g 8 I *"'>

H a r r i s e t a l PR 7j>, 11 ( 5 0 )

p o m e r a n c e PR 8 8 , 4 1 2 ( 5 2 )

P l u m r a e r TANS K> . 2 2 6 ( 6 7 )

Orvini , Maxid Ene-iuia Sucipare14, 541 (67)

5iir.s, JuhnkP JINC 20, 349 (fifij

Ricabarra e t al CJP 47, 20)1 (69)

Resonance parameters SNL-325

RECOMMENDED;

METHUU

a c t

a c t

a c t

pile oac

a c t

a r t

2 - t

a c t

THERMAL

S l'MU.

• ( m )at-

a c

VAl

I 1

^ (

•î . Î

) . 1 -

• " • •

u

( j

'J

•J

2

, !

. j

•<•>

Lfc

.a

KESOKAÎ.'CE

KYM13.

I

a b - or. r

VALUE

1 1 0 - 2 0

i ;

l i C

S VMS.

1/9°

i / o -

VALUECOMMENTS

available. 100% "-decayis assumed tn F1SSPR0D.

Production o£ 1.3 mactivity

Production of 60 dactivity

Corrected for resonanceself-shielding

Au std.

Au Htd.

Resolved r e s . , 2Jfi to192 eV: Tiax. c o n t r i t ,from 21.6 =V (90%)

Production of 1.3m Sb-i:4mi s taken to he ncgl i çji-ble .

Page 60: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

i ^

I i - i i

g ;

s «

- 51 -

v. » ! a

s !

Page 61: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

5 2 - T e - L 2 2_ I

1 . P o r a e r a n c e PR £K3, -112 152? { p l i e M e

Resonance pa rame te r s MIL-:2b

RECOMMENDED

THKKMAJ.

S2-Te-123

1. p™»tanci : PR 8 8 . 412 (52)

rtesûnar.cti p a r a m e t e r s BUL-32 5

pLÎe ope !

RECOMMENDED

•j2-Te-124

1 . H i l l PR 26., 333 (4'M

2. "ameranca PR £ 8 , 412 (52)

3. Gvodez, Khazov JETP 9 , 4 39(«I

Resonance parameters OHÏ.-32

pi le ose !

HATIOK

VALUE | bVMB. I VALUE ' S/MB. I VALUh. —̂ f - 4 --

COMMEM'j'S

| '->',•100

', . 5 : 1 . J

U.040.IJ, 02 5

0

Resolved res., 73 to455 sV; max. com rib.from 7 3 eV (90%)

Au std.

Resolved res., 2.3 3 to"164 eV: max. contrib.from 2.23 eV (98t.)

Kel . to • (Te-130 I -T 0. 008 b

AJ std.

Rel. to r(H£-18Ci- 10 b

No resonances absxgned tothis lsetope

I

Ul

RECOMMENDED

C

9 - ( ni ; J . 0 4

Page 62: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 0.3 -

û) X 01

I _ .i. -1. _ . — .

i !5

I i :-•

! 2

Page 63: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

1.

2 .

3 .

5 .

REFERENCE

32-Te-127m U 0 9 d- IT>99%)

52-TC-127 (<J. A h r )

52-Te-12fl

Seren e t a i FR T2_, 6cl8 (47)

Pomerance PK 8» , 412 (52)

Mangal , G i l l NP 2 6 , 542 (62)

Bishop at ai MF <>0, 2-'.i (64)

Maxxa a t al USE ii_, 88 163)

Resonance paranieters DîtL-rZ^

J

RECOMMENDED

5 2 - T e - 1 2 9 n i ( 3 4 d ; I T , b 4 S )i

METHOD

a c t

pi le ose

a c t

a c t

a c t

SYrtb.

a b

' a b

' • ( m )

ac

àc

ac

> 9" ab

9 (m)

at

A

a b

THERMAL

1

-

1

VALUE

( bJ )

, 0 )

O . 0 1 r / . 0 .

•J. 1.1 : i

0.3-0.

0.118-0.

ù . ' j l û i O .

C . . 0 0 . 0 .

- • . /

0.01 "i

0.2C

150)

00 3

'••;

s

0 2 7

0 0 1 .

0U 8

ftSSOMAKCF.

SYM».

11'

«is»Rllm)

tic-

Km)ab

VALilE

0.0774tO.OO4^

1.48-0.09

. 0

0.03

1 .5

RATIOS

SYHB. VALUE

0 . 0?

!

COMMENTS

No cross section dacdavailable

No cross section dataavailable

HRnormaiised

Henormalized

No resonances assigned tothis isotope

available

I

Page 64: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 55 -

i f

: 'i u

>0

a:

Çj

uOm

•r

oo_̂

g4

3 «

" ?

CO

* (

VIf. —<

i s i . l

I i -i I

! Hi * i

i

I H

• 1 '

0

\

'S1

.r.

r-

_ . . .

' J

; ;

£)

.ilrï*.

— i

G.-,nf ;T)

s:

r?

O

X

**"

en;

-*l

PF.

-.«1t r

Vi

-T

ti

--'Πi

L/

t-4

U

V0ç

«7.

i n

•jil

— -

r

r-,

-r

•T\

a.

m

i *

m

r\

i i

ua :

tN

u01

ia.

SSc0tnU

. _ _ . . .

,,r"

al

1

j ; ' *"' • ti "jr. ,

. j1 r1

"H •

' ;'• "

l".

- t.

i -' Ti

[ ;

I

i i'• f t

1

i

Page 65: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

1.

2.

3.

4.

S.

6.

7.

a.

9.

10.

11.

12.

12.

14.

REFERENCE

53-1-127

Seren et al PR T2_, 88G (47)

Harris et al Pa J9, 11 f50}

Harris et al PR 80, 342 ($0)

Cclraer, Littler Phil. Sac.A63. 117S (50)

Pâmer an ce PR Bi., 641 (51)

Spivak et al PIC-1 Z_, 91 ',55)

Gruneland ER 86. 93/ (5B)

Klûnentov, Griazev JKE 9,20 (S9)

Tattersall et al JNE A12,3i (60)

Meadows, Whalen KSE 9, 132(61)

jôzefowicz Nukleonika £,437 (63!

Robertson NP 2i 417 (65)

Stavisskii, Shernan Sov. AE13, 1210 (65)

Ricabarra et al CJP 46, 2473 (68)

Resonance parameters

RECOMMEHDED

METHOD

act

act

pile osc

pile osc

pile osr

pile osc

act

react.

pile osc

pulsed n

act

act

act

act

7 •me

SYMS. 1

<j\ .

lb

"ab

y'*aO

'Jac

g!ab

ab

9Bac

-!ac

3D

1

RMAL

VALUR

Ï.'J

'i.7

6.I..O.3

6.W.Û.15

5.96*0.20

6.17=0.20

5.6x0.3

2.7t0.7

6.2

SÏMB.

R1ab

-ab

*ab-urtr

Jab

Ml !.CE

VALUE

1JOtiH

143115

19

i50

RATIOS

SYMB.

1/9-

1/9?

VALUE

> 21

-

24.0*0.5

COMMENTS

Renorraali zed

Corrected for resonanceself- shielding

3 atd.

Harwell B std.

Au scd.

Nci std^ Renorraalizedto 0.S3 b.

Harwell B ai.a Au stds,

tin std.

. Au std.

Resolveû res., 20.5 to29S eV; max. contrib.from 37.8 eV (30%)

in

I

Page 66: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

53-1-128k25.0nr EL 65b, 0~ <M%!

51-1-129 (17 M yr)

1. Eastwood e t a l PIC-2 1,6, 54 (58)

1'. Block e t a i ÎJ5E 8, 112 (60)

t. Pa t t enden e t a l USE r ? . 3 7 1 (63>

ftesor.anc» . pa rame te r s BNL-J25

.. ' RECOMMENDED

53-1-1 JO (12 .4 h r !

1. Eastwood e t al PIC-2 _16_. 5-î (58)

RECCMHEÎ./ED

5 3 - 1 - 1 J IO.C3 d 99.4^ to xa-131?)

1. Venner.t. Thode JIHC i, 213 (ja>

2. H-îlp'îrir, r)ru3:-hel ORilL-3488,15 < 6 31

METHOD

act

t of f

t oï £

a ex

HÎFÎBS spec

act

THERMA',

SYHB.

q B ( g ;

ac

~ A b

. <i

" ab

g îab

. î b

/,

(' ac

q'" ac

9\b

VALUE

: . ; . 5 i2

31*4

2ÉJ.O±2.C

0.1.1,0.03

: B

1 g r 3

13

51*40

-- 0 . 7

1

RESONANCE

SYMJ3

RI ac

"ab

I .at>-unr

RI

VAiUE

36-t4

10J:2

12

23

-81

. 11

RATIOS

SYÎ5B. VADUE

i

!

i

1-128 is not listed inFISSPROD. The programassumes 100% t-decay (cannot handle electron con-version). Since 1-128 isformed only by capture in1—127, and both decayproducts have :<1, thisassumption results in anegligible error

Co s t d .

Resolved r e s . , 72.4 to153 eV; max. con t r ib .from 72.4 eV (1S%)

Page 67: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

53-1-133(21 hr; 97% to Xe-133gJ

53-1-135(6.7 hr: 27% to Xe-135m)

54-Xe-12B

1. «acnaitsra, Thode PR 80,296 (50)

2. Tilbury, Kramer NSE 31, 545~(6B)

Resonance paranctere Paris Ij119 (66)

RECOMMENDED

S4-Xe-129m (8.0 di IT 100%)

54-Xe-129

1. V Jnamara, Thode PR B0, 296 (50)

Résonance pavametsrs paris I,119 (66)

RECOMMENDED

METHOD

mass spec

act

mass spec

THERMAL

SYMD.

Aaab

A13 ah

A"c

grim)ac

A°ab

A

"c

*'*

VALUE

(IS)

(15)

< 5

0.43i0.10

»• 1..6

0.4

4.0

(50)

45*15

S.OrO.3

40

P-. ..1NAUCE

SYMI>.

rab

I .ab-unr

VALUE

'- 110

10

100

220^4

3.3

22tl

RAi 10S

SïMB. VALUE COMMENTS

rio cross section dataavailab3 e

Ho cross section dataavailable

Au std.

237 eV res. Isotopeassignment uncertain.

It is assumed that the237 eV res, belongs toXe-128 and o(g)/e(ffl)<*lO.

Ho cross section dataavailable

Au std.

00

Page 68: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

54-Xe-130

1. Mam.mara, Thode PR 80,296 (50)

i. Tilbury, Kramer NSE ,31,545 168)

3. Kondaiah et al NP A120,329 168)

Resonance parameteraParis I, 11.9 (£6)

RECOMMENDED

«

54-Xe-13J.ni (11.8 d; IT, 100%)

54-Xe-m1. Macnamara, Thode PR 80, 2-J6 (50)

Resonance parametersParis I, 119 (66)

RECOMMENDED

METHOD

mass spec

act

act

mass spec

THERMAL

SYMB.

A

c

g?(ro)ac

gs(ai|ac

"'ab

9*(p)ab

99(9l3D

ab

. o' ab

g°'ab

VALUE

'• S

0. 34t0.08

0.445.0.17 0

-- . 2rj

0.4

4

( 50)

1^0.15

fcbr 3

100*

RESONANCE

SYMB.

^ b

'ab

ab-unr

^ b

VALUE

••14

1

12

827.-40

5

B30

RATIOS

SYM3. VALUECOMMENTS

AU atd.•

228 eV res. -Isotopeassignment uncertain.

It is assumed that 228eV res. belongs toXe-130 and o(g)/: (m) *,10

Wo cross section dataavailable

Resolved res., 14.4 to283 eV; max. contrib.from 14.4 eV (97%)

I

en

* irradiations of ref. 1 in NRX. Assuming r.'T'To - O.Û25 and 1 = 830 b then g- - 120 - ( 2/.' • ) ( . 0ic) (830) = 97 b

Page 69: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

54-Xe-132

1. Macnamara, Thode PR BO, 296(50)

2. Tilbury, Kramer NSE 31, Z-\*>!68j

3. Kondaiah et al SP A120, 329(68)

Resonance parameters Paris 1,119 (66)

RECOMMENDED

54-Xe-133m (2.26 d. IT. 100%)

54-X6-133 (5.27 d)

1. Kennett, Thode JINC S_, 253 (58)

RECOMMENDED

METHOD

mass spec

act

act

mass spec

THERMAL

SYMB.

c

g°(m)ac

'"ic"a'(ra)

ac

gs(g)ac. s

""ab

9?ig»gS(g)

A

'ab

c

ab

VALUE

< 5

0.53iO.lO

0.05.0.02

0.O3iO.005

0.415i0.045

0.01

0.04

0.45

(50)

188:B9

190

RBSOHANCE

SYMB.

Xa b

db-unr

'ab'^1

VALUE

0.45^0.03

2.2

G.2

2.4

HAT I OS

SYMB. VALUECOMMENTS

Au std.

Au std.

One resolved res. at

510 eV

From spin assignments

for 133 ni and 13? g it

is expected that

8(gJ/3(n)-ao.

No cross section dataavailable

oI

Page 70: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCESYMB. VALUE

RESONANCE

SYMB.COMMENTS

54-Xe-134

1 Macr.amara, Thode PR 80, 296(50)

2. Kondaiah et al NP Ai20. 329(68)

Resonance parametersParia I, 119 (66)

mass spec

g ' (mlac

ab

G . 0 0 ' 0

I 0 . 2 b S t 0 . 0 2 0

O.23tO.O6ab

ab-unr

4.3*1.;>

2.2

One resolved res. at451 eV.

RECOMMENDED

54-Xe-13 5m (16m: IT, 100%)

ab

ab

ab

0.00 3

0.2b

I . (m)ah 0.1

6

(50) No cress section dataavailable

54-Xe-135 (9.16 \

, Thode PR 8J3, i'M>

2. Breses t l UT. al J1KC 22, i l 7

( frbl

1. Kondaiah irt al NA Al^JO, !?"*(bHI

Hesor.flr.cc pur-*ne?t ei sP i n s I . 1 1 * ( fc f> l

There have l»een nomeasurements s ince I960.The parameters rscou-raended by Fumner lAKEW-R 116 (1962)) give agood f i t to the tirae-of-f l i g h t and i n t e g r a l data

No r e s o n a n c e st o t h i s l a o t ' i p

Ht-'OHMENDED

Page 71: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

55-C3-133

1. Seren et al PR 72. 888 (47)

2. Harris et al PR 80, 342 (50)

3. Pomerance PR §J_, 643 (51)

4. Curamins AERE R/R 2333 (57)

5. Bayly et ai JINC S, 259 (58)

6. Bidinosti et ai PIC-2 ^5, 459

(58!7. Klimentov, Grigzev JNE 'i_r 20

(59)

B. Tattersall et al JNE Ali., 32(60)

9. Lyon NSE 8, 378 (bO)

10. Eiland et al KAM.-2000-11,111-30 (faO)

11. Baerg, Bartholomew CJC 38,2528 (hO)

12. Brown e t a l JNE fil 3 , 1*1 (61)

1 3 . V ida l CEA-H-248b (64 ,

14. S u n s , Juhnfce JINC _3_2, 349 (bd)

Resonance p a r a m e t e r s BNL-325

METHOD

pile ose

pile ose

pilt? ose

pile ose

pi le osc

THERMAL

RECOMMSKDED

act

pile os-

act

ab

ub

' se

VALUE

31 : 6

38. 3

30: i . 5

-'8. J.l .il

J0.4-. 1 .7

•40

.' Ar.i

J ... 4 G . 'i

i 'l. i •- J . î

RESONANCE RATIO:.

M 5 i J 5 I

.; 14 -. 19

45 i

VALUE

Kenorwalized

B Std.

Au Stc>.

Harwell B Std.

Mi std.

Rccj(Co)=10( r. T/T0»-0.05)

I 71.

ed res., 5.9 to470 eVr max. ccntrib.from 5.9 eV (SIM)

Page 72: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

5 5 - C s - l 3 4 ( 2 . 0 5 yt I

1. Eastwoori e t a l PIC-2 1'J, 54 (

RECOMMENDED

J5-CS- L iS (2x10' .ri

1 . Cackir .q e t *1 NRDC-107 ( SH i

2 . Eastwood e t î l PIC-2 J j i , }4 ( 1 ^

55-Cs- 1 <h I 1 .i d .

HKâlïJAKCE

T"ï.Mh. T VALUE

COMMENTS

St -p

i o - l l a - : . i 4

1 . ^ ^ r a ^ r û i i i / e PH. H_M . Vil ' ; - . - , :

H a ï . s e t i : NI1 .•_ . . H • | . ;

) . « H : . ; . i : . i •;: . • ' . . •

Co t t r l .

, No c r o s s s e c : , j n fj.it,i a v a l J i 'bJ e

!

• 4 -ned that

Page 73: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

5&-Ba-J35m (28 .7I T ,

56-B3-135

1. Pomerance PR 88 412

Rusunance p a r a m e t e r s

RECOMMENDED

56-Ba-li6

1. Poneranca PR 88, 412

Resonance parameters

RECOMMENDED

56-B.1-137

1. Pomerance PR go, 412

Résonance parameters

RECOMMENDED

h r rlOC'X)

!52)

DHL-325

(52)

Bl.'L- 32 5

(52)

BHL-325

METHOD

pile osc

pi Le ose

SYMIl

! c

* ' a L

CJ"ab• 1

" db

;J'ab

" .-it.

* \ »

THERMAL

VALUE

b . 8 • u

.' . 1 - u

'J. tl

(J. Ji l l .

J . 16 .- 0 .

0 . 4

"J . 1 r 0 .

0.U5

!.. 1

a

2

•1

Ù6

4

rtESOr

SYKB.

ab- .ini

' . *

ab-urtr

ab-unr

l a b

1ANCE

VALUE

9 0 --5

y

1 0 0

1 fa . 3 T 1 . i

1 . f e i O . J

0 . 3

2

KATIOS

SY.HB.

~ ~ "

VALUECuMMEl.fi,

F o r m e d o n l y by - a p t i i r e

in Ba-134. NoL inc ludedin PISSPROD

Au S t d .

ReLolved r e n . , .? 4 . A t c4bt eV: majî. c o T i t n b .frun 24 .4 eV ( Ï'J.>.)

Two r e s o ] v e d r e s . , 102and 511 f?V; max. c a n t r i b .îicim 102 cV (M4xi

Au s t d .

Resolved r e s . , 419 t o1346 eV: max. c o n t r i b .from -419 eV (&5x)

Page 74: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

5 6 - B a - 1 3 8

1 . S e r e n e'. a i Vf _? 2 , EiS8 ; 4 7 i

2 . S u n y a r , G u l d h . i b v i :•" _J; . lH'JI -I • < I

3 . P u n i e r a n e e PK 8 b . -11 I C b 2 |

• l . L y o n USE 8 , I : p I» . ' ! )

5 . K r . i m i a r , W a l n i r : ' r~ r ^ l , *.~b (< . )

b. RiCdbair.t e t al CJP 4H, 24" J( t H 1

R e s c i i a r : "t p a l w i i - ï c r s B N L - i i : i

i Ea.-."»•.> ,J f t . . . l i . - . . f . -.-1

F.v' *IMI•".' ' '.'

IHt.HMW.

...4 -.-

. -VMP. i-;j,"^COMMENTS

Renorrna l l . -ed

/>•. S l d .

Nt ieforid'i:t- a ̂ -̂ ] jited tu

I

Page 75: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

1.

2.

3.

4.

5.

6.

7 .

8.

9.

10.

11.

57-La-139

Botl.e, Z.Naturf. I, 179 (46)

Seren et al FR 7_2, 88b (47)

Harris et al PR EK), J42 (50)

EeriDist et al J.phys.Rad. J^,531 (51)

act

act

pile osc

pile one

RESONANCE

Pranerar.ce PP. §2, 641 (51) | p i l e osc

Spivdh e t a l PIC-1 Ji. 91 (55) I p i l e osc

Cummins AERE R/H-23?3 (57) | p i l e os,:

Lyon USE 6, 378 (60) j act

KonJcs e t ai ANL-TRAN'S-lt>8 (64) r eac ti

O'Drion et ai ùRML-3^94, 4 (b6i ! act

Rogers, Scoville TANri JJ5, 259 react(t>7)

Kesonance parameters BHL-325

a b

••1U

8 . 4 - 1 . 7

9.fc

•J . 2 : 0 . •!

'i.L'

a.i

i J . 1 8 t 0 . 0 5

SYMB. T

' a b

RATIOS

SYMB. | VALL'I

1 4 . f i U .

11 .2 - C

1 9 r 1

I ! 9 . b ! 1 .ab

CO14HENTS

j

Ho Std.

Renormall/ed

ri 3 td .

llairwc: 1 B S t d .

K,-.d ( Co ) - 10 ( n '•! /T „ ,. ( i.

Au :- td,

T V J rc- so i ved rv •=.

i-or.tr i h . i rotn 7 *.'

'-'

. -1 t'

. 7 3

V

1

RECOMMENDED

Page 76: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

1.

1.

2 .

3 .

4 .

5 .

1 .

57-La-l<10 (40.2 hr)

O'Brien e t a l ORHL-3994, 4 (G6)

RECOMMENDED

58-CS-140

Bothe Z.Naturf. I, 179 (46)

pomerance PR Sij), 412 (52)

Lantz e t a l NSE 10, 302 (64)

Alstad et a l JINC 29, 23 55 :67)

Ricabarra e t a l CJP 46, 247 3(68;

RECOMMENDED

5 8 - C 5 - 1 4 1 ( 3 3 d)

l - an t£ e t a l NSE 2 0 , 302 (f ,4l

RECOMMENDEE

a c t

a c t

pile osc

a c t

ac*-

a c t

mass s p e

THERMAL

SYMB.

'3'ac

VAI.UE

2 . 7 : 0 . 3

2 . 7

1

? \ b

' 3 ? a c

g ' a b

|rc

c

1

<D.6

0 . 6 b • 0 . 06

0.59•0.0b

0.54:0.04

. . _ l

RESONANCE

SYMB.

1

RI

Î •"" t "

a b

KIac

RIac

I a b

0

0 .

VALUE

69r4

7U

48,0.05

49 » 0.03

0. 24

I RATIOS

SVMB.

IVALUE

r f

0 . 4 1 2 v r . . o 3

_

. i

1

11

|

J.I1

Ho Std.

Au Std .

Ad Std.

.lu Std.

!

Page 77: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

1.

2.

3.

4.

5.

6.

1.

1.

REFERENCE

58-Ce-142

Both? Z.Naturf. ±, 179 (46)

Pomerance PR 8j3, 412 (52)

Vaffe et al CJC _3_i. 1 0 23 (56)

Lyon NSE 8, 378 (60)

Alstad et al JTHC 29, 2155 (67)

Ricai.^rra et al CJP 46, 2473168)

RECOMMENDED

58-Ce-143 (33 hr)

Roy, Yaffe CJC J34, 238 i."^)

RECOMMENDED

58-Ce-144 (284 d)

Lantz NSE l^_, 289 (60)

RECOMMENDED

METHOD

act

pile osc

act

act

act

act

act

act

SYMB.

9°at.

g? a b

A

CJC

r\

ac

A

" ac

A

"ab

' ?a c

THERMAL

VALUE

l.-J

U . 6 b • 0 . Ofi

'j.ya-u.ob

0.31

0.94^0.09

0.90

6.0:0.7

6.0

I 1.00i0.10

1.0

RESONANCE

SYMU.

KIac

T~at>

R I a c

VALUE

1.&I0.2

1.0

j1

2.60i0.26

2.2

RATIOS

SÏHH.

1/g5

VAMI?

0.748,0.005

|

Ho

Au

CO

Kcc

Au

Au

COMMENTS

Std.

Std.

Std.

i(CoJ.10ir/*A.-3.05)

Std.

Std.

00

I

Page 78: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE METHODTHERMAL

SYMB. VALUE

RESONANCE

SYMB. VALUE

RATIOS

SYKÊ. VALUECOMMENTS

50-pr-141

1. Bothe Z.Naturf i, 179 (46)

2. Seren et al PR 7_2, 8 3 8 <47>

3. Harris et al PR 79, 11 (50)

4. Panerançe PR 8B, G41 (51)

5. Spivak et al PIC-1 j>. 91 (55)

6. Cummins AERE R/R 2333 (57)

7. Eiland et al KAPL-2000-li,111-30 (60)

8. Lyon NSE 8, 378 (60)

9. Zimmerman i?t a l KP R9S, 683(67)

Resonance parameters BNL-32 5

pile osc

pile osc

pile osc

act

crys spec

17

10.1*2.0

g? . 11.6t0.6ab

i l .4 rO 2

0.4

Ho Std.

Repormalized

Au Std.

9".,

R Ia b

9.2±L.O

10.-5

11.5 .1 .0

0 . e- 9 . 2

R l

12:2

ab-unr

Red (Co) =10{,"TA. -~0. 05)

Reaolvnd r e s . , 50.5 to957 eV; max. contrxb.ixcm 235 eV (30>,)

RECOMMENDEU

5?-Pr-142 h r )

1 . S m i t h , R e e d e r JCP ^ 3 , 2LC8(55)

al;

| Co std.

Page 79: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

59-Pr-143 (13.6 d!

1. Eastwood et al PIC-2 16, 54 (ri8)

2. Roy, Roy CJP YJ_, 907 (59)

RECOMMENDED

59-rr-145 (6.0 hr)

60-Nd-142

1. Des» et al PR 76, 300 (49)

2. Pomerance PR 88, 412 (52)

3. Walker, Thode PR 90, 447 (53)

4. Cabell, Wilkins JINC 30, 897(68)

Resonance parameters JINR-P3-3564 (67)

RECOMMENDED

METHOD

act-

act

mass spec

pile ose

mass spec

mass spec

THERMAL

SYMB.

A" ac

o

9?ab

A

AJC

9?ab

ac

*\

fi*ab

* • >

Vf'.UE

126»14

90tl0

100

(30)

<12

19.3^2.0

13,5

IS.66*0.73

0.02

IB.7

RESONANCE

SYM.'. J VALUE

« a c

^ b

'ab-unr

>ab

190^25

150

0.2

0.02

0.2

RATIOS

SYMB. VALUECOMMENTS

Co SUl.

Co Std.

No cross section dataavailable

Au Std.

Rel. to 5(Nd) = 48 b

Co Std.

Resolved res., 1685 to99Q0 eV; ma*. contrib.from 1685 eV (40%)

o

Page 80: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

60-Nd-143

1 . Hess e t a l PS» 7_t». 300 (49)

2 . Poraerance PR 8 8 , 412 (52)

3 . W a l k e r . Thode PR 9 0 , 447 (53)

4 . Hay, Pat t tmden NRDC-113 (59)

5. T a t t e r s a l l e t a l JNE A12, 32(fcO)

6 . F e h r , Hansen KAPL-20OO-12(60)

7. C a b e l l , Wi.lk.lns J1NC 30 , B97(68)

Resonance p a r a m e t e r s BNL-325and JINR P3-3564 (671

RECOMMENDEr

METHOD

mass spec

pile osc

mass spec

crys spec

pj.le osc

react.

rcass spec

THERMAL

SYMB.

c

*8.b

A

C

3 a b

»5ab

A

"*ab

°c

^ALUE

2 4 0

304t?4

334,12

343^20

:)3BîiO

202.-25

31f. .2 tH.6

i ° 2 . CM 0 . 8ab

RESONANCE

SYMB.

^ b

^ b

ab-unr

J a b

VALUE

< 5 0

56-. 3

5. 3

60

i

RATIOS

SYMB. VALUE

Au S t d .

Rel. t o .7 (Nd) = 48 b

Av. of e a r l i e r data(NRDC-103, JME 7, 199(58), PIC-2 16,~44 (58)TNCC(UK) -20 (57))

Harwell B Std.

Quoted for use with nv.Here corrected for usewith n», .

Co Std.

Resolved r e s . , 56 to840 eV; max. contr ib.from 56 eV ( 3 3%)

Page 81: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

60-Nd-144

1. Hess et al PR 7J>, 300 (49)

2. Pooerance PR 88, 412 (52)

3. Walker, Thode PR 90, 447 (53)

4. Cpbell, Wilkins JINC 30, 897(68)

Resonance parameters JINU-P3-3564 (67)

RECOMMENDED

60-Nd-145

1. Hess et al PR 76, 300 (49)

2. Panerance PR 88, 412 (52)

3. Walker, Thode PR 90, 447(53)

4. Patienden PIC-2 16, 44 (58)

5. Tattersall et al JNE A12, 32(60)

6. Cabell, Wilkins JINC 30, 897(68)

Resonance parameters BKL-325and JINR P3-3564 (67)

RECOMMENDED

METHOD

mass spec

pile osc

mass spec

mass spec

mass spec

pile osc

mass spec

crys spec

pile osc

mass spec

THERMAL

SYMB.

AJC

A

C

A•3

C

*3ab

A1C

Q

'«ab

VALUE

<1 S

5.05-0.6

<6

3.56TO.3O

2.0*0.6

3.6

<30

54±4

37 rO

51i3

49.511.5

41.2x0.7

10*5

45

ASSONANCE

SYMB. [ VALUE

ab-unr

*ab

Ic

1ab-unr

Kb

3.4x0.3

0.2

3.6

240i35

250x50

9

250

RATIOS

SYMB. VALUECOMMENTS

Au Std.

Co Std.

Resolved res., 374 to3570 eVr max. contrib.from 374 eV (70*)

Au Std.

Rel. to 3_(Nd) = 48 b

Harwell B Std.

Co scd.

Resolved res., 4.4 to660 eV? max, contrib.from 4.4 eV (50%)

I

to

Page 82: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

60-Nd-14b

1. Bathe Z.Naturf. I, 179 (46)

2. Hess et al PR 7J6, 300 (49)

3. Pamerance PR SB. «112 (52)

4. Walker, Thode PR 90. 447 (S3)

5. Alstad et al JIHC 2V_, 2155 (b7)

6. Mowatt, Walker EANDC (Can)-38,4 (68)

Resonanre parameters JINR P3-3564 (67)

RECOMMENDED

60-Nd-147 (11.1 d!

60-Sd-14B

METHOD

act

mass sppc

pile osc

mass spec

act

act

i

THERMAL

SYMB.

c

C

c

ab

1

VALUE

l.R

^20

10.2»U.fa

-,

1.3:0.1

1 . B • f !. 3

0.14:0.03

1 . J

( 50)

RESONANCE

SVMli.

RIat"

ab-unr

. . . . . |

VALUE

3.0,0.3

1.br0.2

0.2

2.0

' j "- -1 H"

RATIOS

SYMB. VALUE

^ • - < - • - -

• - J.

COMMENTS

HO Std.

Au Std.

Rel. to gs(Nd-14S)=2.54

Resolved res., 360 to402b eV- max. contrit.1 rcm 360 eV (4O'*J

No croBa section d^tnavni1abit

Bo t h e Z , N * ; t J f f 1 , ]

Hi*«ip e l \ . i'h J , Ji

w a '. - '.• r , Th- -Jt- ['H 4KJ

H i i : e t i i TA.N. T .

\ ï s* î ' i '•* ^ . • I TIC I

, 4 4 . ' i => i j

i '

, p i l e o n e q~ a

i

i â : t q\

H o S t d .

'u std.

Page 83: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE METHOD

60-Hd~150

1. Hess et al PR 76, 300 (491

2. Bomerance PR 88. 412 (52)

i. Walker, Thode PR 90, 44? (53)

4. Sehgal et al BP 12, 261 (59)

5. Alstad et al JINC 2±, 2155 (67)

Resonance parameters JINR P3-3564 (67)

mass

pile

mass

act

act

spec

ose

spec

THËKMAI.

SYMB.

ac

ab

- -15

J.Uil.5

< 12

1.5r0.2

1.0*0.2

•). 3-r'J. 1

REiiON'iUtCE

SÏMB. VALUE

ab~unr

1-iil-J

14±l.r.

0.3

RATIOS

SYMB.COMMENTS

Au std.

A;J std.

Kesolved res., 79 to3840 eVr n-ax. .̂.iitribfrom 79 eV

RECOMMENDEDab

61-Pm-147 (2.65 yr)

1. Inghra» e t a l PR 7_2, 85 (47)

2. Gorshkov e t a i JKE i l B. 69 (58)

3. Harvey e t a l P I L - 2 16_, 150 (58)

4. Bidinost i e t a l PIC-2 1_5, 459( 58 )

5. Schuman, Berceth NSB L2, 519"(62)

6. Fennei; Large JINC 29, 2147 (67)

7. Kirouac et al NBS Spec. Publ.299, 687 (68)

8. Wowatt, Walker (to be published)

Resonance parameters of re'f. 3 5?

act

mass spec

t of t

nass spec

art

mass spec

•iy)ac

14

93'.''I !

180f 3(1

200 T -JO

\11s11

7 3 t 7 kl (m)

Rlc'.g)

<3 '(ml

^ ° 1,31

88. IL ab

ab---ir.r

1700-r 2 50

720-20C

80OJ.250

2 300^260

70

Co std.

Assumed - BbHot scatt- .ce analysis.

Co strt.- r/T/1, - 0.003

Resolved res., 1.04 to115 eV; max. con crib,from 3.4 eV (BO*)

RECOMMENDED BO

90

I (in)ab

1050

1150

Page 84: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

6i-Pm-14Bm (40.6 d:IT, 7%)

1. Schuman, Berreth NSE ^2, 519(62)

2. Fermer, Large JINC 2V_, 2147( 6 7 )

RECOMMENDED

METHODTHERMAL

SYMB.

61-Pm-14Bq (5.4 d)

Schuman, Berreth NSE 1_2, 519(631

RECOMMENDED

61-Pm-149 (5J ht)

K o n d u r a v ? t ?.i JNE £_0, B Î 4( 6 b )

I

M o v a t t , W a l k e r NBb ^ p e c . P a b . j•!'•»*. 1 2 4 1 (bB) :

mass specI •••

VALUE

RESONANCE

SYMB .

RATIOS

VAi.UE SYMB. | VALUE

i 2<J- i) 1J-1

r - - -

COMMtMTi

Mainly tlieraal

Co ccd.

|- - 1 1. _ i _ _ 4-

i !

«l.unli- epi-Cd

RECOHMENDED

j l - P m - 1 lï i 2H h n

: . W.t i \*.>r SB;; p e r . E>_jb. , d e p l ,^ • w , l i ' H (bH) ,

REC'IMMESDE-..

• - ! •

Page 85: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

62-Sm-147

1 . T a t t e r s a l l AERE R/R 2459 (58)

2 . Gorshkov e t a l JNE I I 8 , 69(58)

3 . Fehr, Hansen KAPL-2OOO-12,133 (60)

4. T i t t e r a a l l e t al JNE A12, 32(60)

5. Fenner, Large JIKC .29, 2147(6-,)

6. Forraan, White NSE 28., 139 (67)

Resonance parameters BNL-325

RECOMMENDED

62-Sm-148

1. Wnittau AAEC/TM-443 (68)

Resonance parameters BNL-32 5

RECOMMENDED j

METHOD

pile? esc

nu.» s s spfcc

react

pile ose

mass apec

mass spec

1mass spec

THERMAL

SYMÏ1. VALUE

I

'<-

H7:bU

i()UO' SO

• « L '• > 0 " ' U

* • < :

* % b

0

" 'ab

* \ *

Su- 1

7 5 : 11

11.-}

4 . 7 3 r O . U

ù

4 . 7

RESONANCE

SYHE.

a b

R 1 c

•* iib-unr

^ b

X a b

VALUE

*1350

falUr 20U

500^50

100_

too

0

Q

RATIOS

SYHfl. | VfiLl'E

:

._ . .

COMMENTS

Co 3tr!.

T,. « 127 t 13=C

R^^olvcd r e s . , 3.4 t.oL»c> eVr max. c o n t r x b .iiuni 3.4 eV (32%)

No resonances ass igned tot h i s i s o t o p e .

I

•vj

Page 86: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

1.

2.

3.

4.

REFERENCE

62-Sm-149

Inghram et al PR79,(50)

Gorshkov et ai JNE IJ

Tattersall et al

Bidinosti et al

AERE

PIC-2

271

_B, 69158)

R/R 2459(58)

15, 459(58)

METHOD

nv3~s

DàSS

pile

mass

spec

spec

C S C

s per

THr RMAI.

"sYMH.T V Al. ll£

5. Anlkir.a et ai PIC-2, 15, 446 j mass spec

i6 . P a t t e n d e n P I C - 2 ±b, 44 ( 5 3 )

7 . M e a d o w s , Wha le r . NSE <i_, 132 [hl,

8 . A i t k e n , C o r n i s h J INC }J_, b ( b l )

9. Pokclowstti et al Nukleo:»!1. b_,245 (64)

l i . Albert et al Kernenerqve 10.25 Ifc7>

c r y s s pe :-

p u l s e d r.

m a s s s p e c

p i l e o s e

t ot f

pi le ose

S V M B . I

HbSONANCE I

VALUE |

. -i^. -, c?,

( 4 ' : ri) i l .

( h b . B • \J . 3 [ i k 1 J

l 4 1 . 5 • l . 1 I 1 '-•

( 4 1 . >* - - ! 1 M '

H . A Ï 1 O S

S i ' M B . | V A L U E

COMMENTS

Harvell B Std. Westcott g

Using WcstCDtt q,s

Usirq Westcot t y , s . Alsoagrees wi th • a b ot r e t . tj s l na a p p r o p r i a t e .; . s .

Lsir.u Wes tco t t y , s . Frtxr.qab^q m ' 3ssjai.it; -iftt 3b.• 1 i. ti?,.

From aa^(BiTi) aspuT..nq

net ab . = 13 .9* .

I

RECOMMENDED U=e v.-ith Kestcot t ij,!.Vtil LitiS

Page 87: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

62-Sra-150

I. Aitken, Cornish JINC 17, 6(61)

2. Hfllperin et al TANS 5, 376(62)

Resonance parameters DNL-325

RECOMMENDED

62-Sm-151 (=^7 yr]

1. Inghraro et al PR T9_, 271 (56)

2. Melaika et al CJC .33., 830 (55)

3. Bidinosti et al PIC-2 15, 459(58)

4. Anikina et al PIC-2 15, 446(58)

5. Pattenden HSE V7, 371 (63)

Resonance parameters KSE 17.371 (63).

RECOMMENDED

METHOD

mass sper

mass spec

mass spec

mass spec

mass spec

mass spec

t of f

THERMAL

SYMB.

/\ac

Aac

rt

Acc

A0c

Sab

VALUE

10215

98*10

0*1

100

7200

12000

13000*400

8000,1500

1500CU1800

15000

RESONANCE

SYMB.

RI

^ab

ab-unr

^ b

Jab

ab-unr

Tab

VALUE

255,25

245*25

23

240

3300i700

2250

750

3100

RATIOS

SYMB. VALUECOMMENTS

i/T/To = 0.0016

Co std.

One resolved res, at20.6 ev

a Std.

Co std.; NHX irrad(g + rs -v. 0.85)

Resolved res., 1.1 to6.3 eV; max. contrib.from 1.1 ev (6054)

Use with Westcott g,svalues

00

I

Page 88: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

62-SW-152

i. Bothe Z.Naturf 1, 179 (46J

2. Seren et al FR 22. B8B (47)

3. Sunyar, Goldhaber PR 76, 189149)

4. Harris et al PR 22. il (50)

5. Psttenden PIC-2 16, 44 (5B)

6. Tatteisall et al JHE A12, 32(60)

7. Walker, Green CJP 19, 1184 (61!

8. Bernabei et al USB .12., 63 (62)

9. Cabeli JINC 2_4, 749 Ife2)

Resonance parameters BNL-325

RECOMMEKDED

62-Sm-l53 (47 hr)

62-SII1-154

1. Seren et al PR 21, S88 (47)

Resonance parameter

RECOMMENDED

t.;-sn-156 19. i hr)

METHOD

act

act

act

act

crys spec

pile osc

act

crys spec

act

t

act

THERMAL

SYKS.

Ac

ab

ab

ac

" " i i b

* ac

'ab

g'ac

" ab

g'ab

"at

VALUE

J

13T)i27

200:6

209;3Ù

2 Of.

(50000;

*.S:1 .0

- 0

( 3.0!

• -!

RESOHAKCE

SYMB.

RIac

'ab

ac

I ,ab-unr

Xab

VALUE

24ÛC

2B50O0Û

3070=100

29201300

20

3000

-. 0

t

0

RATIOS

SYMB.

1/9°

i/g"

VALUE

12.3

14.5.10.4

(14.b)

i

i

i

COMMENTS

Ho Std,

Renormalized

Corrected for resonanceself-shielding

Au Std.

Au Std.

Au Std.

One resolved res. at8.0 eV

available

1 resonance assigned thisr.dcllde. n'o ~'s listed.

So cross sect it r, dat-iavailable

Page 89: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

63-EU-151

1. Bothe Z.Naturf X., 179 (46J

2. Seren et al PR 72_, B88 (47)

3. Hayden et al ER 7_5. 1500 (49)

4. Pattenden PIC-2 16, 44 (58)

5. Tattersall et al JNE A12, 32160)

6. Bans et al HP 20, 183 (60)

7. Jacks DP-608 v61)

8. Keisch PR 129, 769 (63)

9. Rogers, Scoville TANS 10, 259(67)

10. Albert et al Kernenergie 10,25 (67)

11. Sims, Juhnke JIBC 29, 2671 (67)

Resonance Parameters BHÏ.-325

METHOD

act

act

mass spec

crys spec

pile osc

act

act

act

react

pile osc

act

THERMAL

SYMB.

33(?)

ac

90 (m)ac

Acc

«ab

Aac

ac

VALUE

1700

3830

1900*400

8800

7700i8O

8840*90

1700i300

9350*110

30BOi90

4465*65

RESONANCE

SVMB.

*a*

VALUE

*

<3000

J470

1400

RATIOS

SYMB.

Rl/gS

5<*>/?(9>

VALUE

0.64i0.10

0.56i0.04

COMMENTS

net included in FISSPROO

Ho Std.

Ho Std.

(3-c-ounting only. Correct-ed 25% for electron capt.

Eu std.

Harwell B Std.

\u Std.

Au Std.

Au Std.

Resonances with EC>1 eV

00o

Page 90: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFEREHCE

63-Eu-152m

(9.3 hr; EC, 23%: &~ 77%)

53-Eu-152

(12 yr: EC, 72X 0~ 28%)

1. Hayden et al PR 7_5, 1500 (49)

63-EU-153

1. Hayden et al PR 21» iSOO (49)

2. Pattenden PIC-2 16, 44 (5d)

3. Tattersall et al JSE A12, 32(60)

4. Rogars, ScovilU- TANS 10, 259(67)

i. Sims, Juhnke JIKC 29, 2671 i67J

Resonance parameters BHL-32b

ki-COHMEKSED

METHOD

mass spec

mass spec

crys spec

pile osc

react

act

THERMAL

SYMB.

r

r-ac

3ab

-' ac

9

"ab

VALUE

5400

406

448il6

3.1 9t 5

12

450 [

RESONANCE j RATIOS

SYMB.

R I a c

1

I .ao i

VALUE j SYMB.

1230±100

1Ù33

1200*120

3 50

1500

VALUE

1

COMMENTS

Hot included in ^ISSPROD

No included in FJ1SSPR0D

Rel. to E-J

Rel. to Eu

Harwell B and Au rtds.

Au Std.

Resolved res., 0.46 to24 eV; ma*. ccmtrib.fxom 2.46 eV i3i%)

I

CD

Page 91: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

63-EU-154 IB v r )

1. aayden et al PR 21, ^500 149!

RECOMNENDED

63-Eu-lSS (5 yr)

1 . Hayden e t a l pa 7J5, 1500(49 )

2 . Mowatt ( p r i v a t e coran.)

RECOMMENDED

63-EU-156 U S d)

63-EU-157 1 1 5 . 2 hr )

64-Gd-154

1 . Dobrozemsky e t a l P a r i s . ' ,495 (66)

2. Gishanin et al Sov. J.At. En. 22_, 144 (67)

Resonance parametersINDC-260 E, 114 (68)

RECOMMENDED

METHOD

mass spec

mass spec

depletion.

mass spec

mass spec

THERMAL RESONANCE

SYMB.

A

c

/̂-ab

A

K>A

'at»

j » b

A

'ac

A

°cA

t S a b

•3'ab

VALUE

1490

1500

SYMB.

1

13400

4200

4200

(2000!

(2000)

iQ5*n

100i-20

2.6*0.5

85

I

I c

lab

^ab-unr

i

VALUE

303)31

180tl5

34

250

RAT

SYMB.

I OK

VALUE

1

COMMEIITS

Eu Std.

Eu Std.

Preliminary

No crojs section dataavailable

No cross section dataavailable

Rctl(Co> = 7 . 8 8(r/T/To -- 0.07)

Kesolved r e s . , 11 to244 eV; max. contrib.from 22.4 eV (45%)

I t i s astnunetf that15-20 b. of ref. 1 and2 i s epithermal

03

Page 92: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

64-Gd-155

1. Lapp et al PR 21. 745 (47)

2. Inghram et al PR 79, 271

(50)

3. Pattenden PIC-2 16,, 44 (58)

4. Tattersall et al AERE R/R

2459 (58)

5. Low, Shaltiel PR î.15, 424(59)

RECOMMENDED

64-Gd-156

1. Dobroiemaky et al Paris I,495 (66)

2. Gishanin et a] Pov.J.At.En.22 , 144 (b7)

RECOMMENCEE

METHOD

mass spec

mass spec

crys spec

pile osc

mass spec

niaas spec

mass spec

THERMAL

SYHB.

A

"c

/\

c

T

c

g

ab

c-

c

at-

>

VALUE

69000

41000

RESONANCE

SYMB.

66000^2000

,,800,,,00

94 500

GbOOO

6. 3tl.il

". - . S - 7 . 2

1 *l r 0 t

:. 4

I

!alJ-Jnr

Xab ;

VALUE

7Bi21

«,

< . •

RATIOS

SYMB. VALUE

--"

COMMENTS

Harwell B Std.

Gd rtd.

Rca(Co)=7.0B(r,'T/T1,-_0.07)

; 98^ eV • may . cent r 11>.

r r urn JJ.I tr\ 15C",|

I

00

Page 93: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

64-Gd-157

1. Lapp et al PR 11, 745 (47)

2. Inghram et al PR 22< 2 7 1 <5°)

3. Pottenden PIC-2 _Ub, 44 158)

4. Tattersoll et al AERE R/'R2459 (58)

5. Low, Shaltiel PR JJJS, 424 (59)

RECOMMENDED

64-Cd-lSB

1. Seren et al PR 22» 688 (47)

2. Butement PR Jl< l27& (49)

3. Lyon NSE 8, 378 (60)

4. Mangal, Gill NP 41, 372 (63)

Resonance parameters BNL-325

RECOMMENDED

METHOD

mass spec

mass spec

crys spec

pile osc

mass bpec

act

act

act

act

THERMAL

SÏMB.

" c

1

"T

ACc

o

"ab

A

" ac

."•

ac

A

ac

' 8ac

" ab

V.VLUE

240000

59500

264000.4000

214000i;2000

224000

264000

- 3

4.5

3.69

2.78rC42

1.2^0.2

2.8

RESONANCE

SYMJ3.

ab-unr

VALUE

i

S8tS

5

60

RATIOS

SYHB. VALUE COMMENTS

Harwell B Std.

Rcd(Co)=10(r/T/T0o0.05)

Resolved res., 22.3 eVto 920 eVj max. contrib.from 22.3 eV (80%)

I

00

Page 94: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

64-Gd-159 (18.0 hr)

64-Gd-160

1. Butement PR Tï, 1276 (49)

2. der Mateosian et al ANL-42 3764, (49)

3. Mangal, Gill HP 4_i, 37Z (63)

lNnC-260 S, 139

RECOMMENDED

65-Tb-159

1. Pomorance PR B_3, 641 (51)

2. Alstad et al J1!1C 29. 2155(67)

Resonance parameters BlîL-W S

(

••ECOKMENDED

METHOD

act

act

act

pile ose

act

THERMAL

SYMB.

'ab

ac

ac

* \ b

n *

- \ ,

_ J

VALUE

(50000)

0.17

IJ.l

O.77.-0.11

O.B

4 ' t 4

1 1 - 1

••.•I I . -1

RESONANCE

SYMB.

I .

al>- .nr

1

VALUE

5.710.8

1.7

RftTIOS

SYMB. I VALUE

„ _ j

7.0

--.50,50

? 30-JO

f

4215 |

COMMENTS

No cross section dataavailable

Resolved res.f 222 to142 5 eV: raax, contrîb.from 222 oV (b^X)

Au Sid.

Au Std.

Re sol w d ros, . i. 1 '• to

i 'it- oV • max . i • T U r , b .

from I \ . 1 eV ; i -J • "'

I

Page 95: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

6S-Tb-160 (72.1 d)

1. Smith et al JCP 25, 502 (56)

RECOMMENDED

65-Tb-lbi iS.9 d)

66-DV-16C

I. House, Frost BAPS 2, 337 (SB)

2. Scoville, Fast HSE JL8, 400 (64)

3. Scoville et al NSB .25, 12 (66)

Resonance parametersINDC-232 (USSR Data)

RECOMHENDED

66-Dy-161

1. House, Frost BAPS J3, 337 (58)

2. Danelyan et al Sov.AE 16, 58(64)

3. Scoville, Fast NSE IjJ, 400 (64)

4. Scoville et al NSE 25, 12 (66)

Resonance parameters BSL-325

RECOMMENDED

METHOD

act

pile osc

react

react

pile osc

t of f

react

react

THERMAL

SYMB.

A0ac

A

°b

A

°ab

°ab

*Sab

>?ab

\b

9Sab

al*

*3ab

aS .ab

g3ab

VALUE

600*100

600

(2000)

130*130

55i9

76±20

60

680.'40

580*50

617±40

583±95

<!3±6

600

RESONANCE

SYMB.

RIab

Jab

ab-unr

Xab

M a b

Jab

ab-unr

VALUE

1160*130

130O±3OO

100

1200

1670±167

825*40

170

1200

Î.ATIOS

SYMB. VALUECOMMENT'S

CO Std.

available

B Std.

AU Std.

Au Std.

Resolved res., 1.88 to85 eVj max. contrib.from 10.4 eV (48%)

B Std.

Au std.

Au Std.

Resolved res., 2.72 to7 2.5 eV; max. contrib.from 3.7 eV (30%)

I

œ

Page 96: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 1.-•« m.

2.

3.

4.

1.

2.

3.

4,

REFERENCE

66-Dy-162

House, Frost BAPS 3., 337 (58)

Danelyan et al Sov

Scoville, Fast NSE

Scoville et al NSE

AE 16, 58(64)

18, 400 (64)

25, 12 (68)

Resonance parameters BNL-325

RECOMMENDED

66-Dy-lbl

House, Frost BAPS J

Danelyan et al Sov.

Scoville, Fast NSE

Scoville et al NSE

Resonance pai-awei-c

RECOMMENDED

, 337 (53)

i\E 16, 58T64)

U3, 400 (64)

IS, 12 (fc6)

5 RKL-32 5

METHOD

pile osc

t of f

react

react

pile osc

t of £

react

react

SYMB

°ab

95ab

o

«?ab

i!ab

- a b

a

0

ato

i

g O a b

ab

*\,

THERMAL

...

VALUE

240*30

140i40

215x16

152*27

^00x70

1 190

22Ot5O

135^15

1 \2111 '3t

j .«.»130

RESONANCE

SYHB.

« a b

Zab

ab-unr

Jab

RIab

!

ab-unr

'ab

VALUE

332OJ-4OO

2450+350

6

2800

1960il76

lB10tL50

70

1900

RATIOS

SYMB. VALUE

1

COMMENTS

B Std.

Au Std.

AU sta.

Resolved res., 5.5 to655 eV; max. contrib.from 5.5 eV (96W

IS Std.

Au Std.

Au Std.

Resolved res., ..? to94 eV- max. cati:z ib.£r<ït 1,7 eV (9ir».|

I

00

Page 97: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

REFERENCE

66-Dy-164

1. Both» Z.Haturf 1, 179 (46)

2. Seren et al PP. H , 888 (47)

3. House, Prost BAPS .3, 337 (58)

4. Sehgal et al NP 12, 261 (59)

5. Jacks DP-608 (61)

6. Shec et al NSE U., J69 (61)

7. Mangal, Gill HP 26, 542 (62)

e Scoville, Fast NSE 18, 400(64)

9. Scoville et al NSE 2j>, 12 (66)

10. Albert, Schumann Kernenevaie1£, 306 (67)

Resonance parameters BHL-325

RECOMMENDED

67-KO-165

1. Seren et al PR 72, 8SS <47)

2. Pgnerance PR 83, 641 (51)

3. Zimnerman et al NP A95, 6S3i67)

4. Mots et al PR 115, 1265 (67)

Resonance parameters BNL-325

RECOMMENDED

j

METHOD

act

act

pile osc

act

act

cry s spec

act

react

react

act

act

pile osc

crys spec

act

THERMAL

3YMB.

g3(g*)ac

ac

A°ab

*Sab

«Sfe)

Sab

'>&>

gS a b

gSLVg§a-D

Sab

HPiSab

VALUE

2870

2700x270

2B70±50

27 50±150

2490,30

< 840

2700

951*240

2600t410

2390t70

2700

58±12

67±3

.1*3

3.5±0.5

19±2

63

RESONA'JCE

SYMB.

RIab

Xab

ab-unr

ab-unr

lab

VALUE

377±34

20

18

630i30

55

VOQ

RATIOS

SYMB.

y i/9»

VALUE

0.175

COMMENTS

Ho Std

Reiiormalized

B Std.

T E O.O2É5 eVa

• ' •

Au Std. Rl above 0.6 eV

Au Std.

Au Std.

frora data of ret .6 . Nodata on half-life ofmeasured activity.

Renormalized

Au Std.

a(E) => 1/v to 1 ev

to 1200 yr Ho1*"1"; relto Sab » 66.5 b

Resolved res; 3.9 to195 eVs max. cont.rib.from 3.9 ev (50X)

00OD

Page 98: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 89 -

TABLE 2

FISSPROD NUCLIDE TABLE

IDENTIFIER CROSS SECTIONS AND RESONANCE INTEGRALS(BARNS)

DECAY CONSTANTS

ELEM .Z.E

OEGEASSESESESERRSEpftKRKRKRKRÔBKRR3SRRSSRSRSRVSRYZRS«YZRzffYZRZRZRNBMOZRNBMOZR

76320 .(77320 .77330 .77340 .7834079340803408135082340 .8235082360 .8336084360 .85360 .8537086360 ..8637086380 .873708738088380 .89390 .89390 .9038090390 ,90400 .913809139091400 .9240093390 .93400 •9440095400 .95410 «95420 .96400 .96410 .96420 .97400 •

TO METASTABLE STATE

or ô08

TO GROUND STATE ^ ^go I •

or è.08

30.00U30.00U42.

.430.00U

.582.4.045

1.00U

700..03

A..421*1.00U1..12

40.00U.005.421.280.84.00.1

5.00U1.*1.6.26

5.00U2..07

5.00U4.14.5

.25.00U1.25.000

.5

14.4**1.3

50.• 09

190.150.2.0

7.

3.02.3

100*.06

'.3

15

6.5.5

22*• 26

100*6.0

25.

j3 -DECAY TOMETASTABLE GROUND

STATE STATE

170400.49800,

54500.

1543.

7.R230000.

1364

1234.22*0,

«2300.

113300.

Page 99: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

- 90 -

MOMOMOTCTCMOHURUHURU

PDHUHHpDRUPDHOPOPOAGPOAGCU«6COPO!rOCOCDtOCOINCDSNSNSNSNSNSNSNSNSBSNSBTESNSB

JE

IESNSBTETESNSB

97420984209942099431994301004201004401014401024401034401O345O10444010446010544010545010546010644010646010V460108460109460109470110460U0471110480111470ÎU4801124601124*01134R01144801154H11154801154901164S0116500117500118500119S01119500120500121501121500121510122500122510122520123500123510123520124500124510124520125500125510125521125520.126500126510126520

02

13

04

10

2.2.14

. 5.00U5.00U

?2..2

. 5.85.21.3

. S.OOU

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Mas» No.Metastable State

bracket! indicate a short-livedleaner (tti ? S h) not lilted inPISSPROD- data

"m" is omitted if no metaetable »tate ia knownor if there ii no significant production* byfission or capture

L E G E N D

Percentage production of iscners byB-decay or fission

Ground stateHalf- l i fe (honours, dadays, y=years)

Fission yield, when divided between metastableand ground state isomeraFractions of yields are shown as percentagesCumulative yields at other masses are not shown. The mass chain i sentered via the ground state with lowest z (direct yields are not shown)

P-decay* I If more than one decay mods i s shown,lsomeric transition* I fractions are shown aa percentages.

Neutron capture*

• Only transmutations listed in this PISSPROD data library or assumed in the program

itself (bracketed isomers always decay instantaneously to the ground state of the

Z+l nucleus) are shown, as described in text.

Fig. 1 Nuclide Chart shoving P-decays, isomeric

transitions ar.d capture transmutations included

in PISSPROD.

Page 103: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

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Page 104: FISSSON PRODUCT DATA FGi THERMAL REACTORSPart I is a compilation and evaluation of cross section measurements for all fission products with half-lives exceeding ~ 5 h in the mass range

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