fissson product data fgi thermal reactorspart i is a compilation and evaluation of cross section...
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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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FISSION PRODUCT DATA FOR THERMAL REACTORS
Part I - Cross Sections
by
W.H. WALKER
AECL-3037Part I
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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
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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
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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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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
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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.
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_ 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
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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,
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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).
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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.
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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.
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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
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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
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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
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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.
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(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.
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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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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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:. 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).
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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
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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
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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 ' )
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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
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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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/28.jpg)
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
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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
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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
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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
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;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
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- 29 -
IL <nt . E - E -
V, G
a: r~-
-r
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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
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- 29 -
î2 §
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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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/37.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/38.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/39.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/40.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/41.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/42.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/43.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/44.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/45.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/46.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/47.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/48.jpg)
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)
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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 - - -
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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
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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 .
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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.
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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> )
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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
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- 49 -
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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
RESOHAHŒ RATIOS
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/59.jpg)
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 .
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i ^
I i - i i
g ;
s «
- 51 -
v. » ! a
s !
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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
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- 0.3 -
û) X 01
I _ .i. -1. _ . — .
i !5
I i :-•
! 2
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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
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- 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
--'Œ i
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
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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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/66.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/67.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/68.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/69.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/70.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/71.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/72.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/73.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/74.jpg)
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
UÏ
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/75.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/76.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/77.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/78.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/79.jpg)
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
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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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/81.jpg)
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
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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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/83.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/84.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/85.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/86.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/87.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/88.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/89.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/90.jpg)
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
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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
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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
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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
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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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/95.jpg)
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
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- 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
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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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/98.jpg)
- 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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/99.jpg)
- 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
. ISO.47
. »*• 'l.OOU
• .3. 17000.. lO.OOU
.15o .3. 5.00U• 10.. 5.00U1* 92.
.3. «2.• 10.. 3.
33.l.OOU
* 2.• 29000.). 0.3. 5.00U
5.00U• 206. -. .08. 0.25U
1.40U.2 0.8 U
5.00U. 1.20U
.2. 50.00U
C ft A A" 1« r»0»00J
* 6.2>6 .001* lO.OOU• 2.8• 50.00U
4.2• 410.
9. .004. 6.5* 6.5
• so.coulO.OOU
. 50.00U1.5
• l.OOU• lO.OOU1* .9
15.P.O••
200.3."*9.
76.4.2•
1100.4 4
17000.fis.2.0
•240.
B
1450»6*•
37.100.47.
.17.
•
20.••
3340*•
15.12.8..
3.S»l.S•
•200*
•
66*
130*5400*
.03•
•
•18*
•9.
32100025000 3740.
2030»
434000.55000.
220.
142600.
31 r.
10700.
91700.
1866'36000.
321
1383
2.971300.
28700.
642.
1337.•
8540.65.1
6420.
![Page 100: 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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/100.jpg)
- 91 -SBIEÏEITEXETEIXEXETE
IXETEIXEXETEvETXEXECSXEcsRA1XEXELSbAXECSRACSBAbALABA
PRi-£PRNOCEPRN'IO
CEfcjOPRNDNDNOPMbMwOPMPM
127510127521127520127530128520128540129521129530129541129S401305201305301305401315211315301315411315403 32520! 32540133530133541133540133550134540134550134560135530135541135540135S501355601365401365501365601375501375601385601395701405601405701405«01415H01415901425*0142590
1435R0143590143600144580144600145590145600146600147600147610147620148600148611148610
.015
.4
.02
.4
OR
«04
• 003
0.2
• 1
R0. 1050
10.0OU50.00U50.00U6.2
4.50.001)*«.50.00U40.
.20l f i .4.50.00U1.
so.oou100.l.oou.45
15.00USO.OOU
190.?9.50.26
HO.2.15.00Uso.oou
3000000.A.95.8.2
15.00U.4.11
5.1.4
9.01.62.7.59
r" m
i l ..90
?o.1».76.
inn.35*5.1.3.630.00045.1.*
sn.oou9f).55*2.5
24000.3000.
•
150.1 -S1 • S
100.•23.
•
220..36•
12.•
3.0
830.*
2.4B
m
•
450.ft.•
in.••*
58.lor.
•
t
17.«
2.0.?.
11.13.70.
.24
•13.1.0•.2•
15f).60.2*23.6»
250.2«0*
115fl.600»20.
•0
736
23feO
10300
3310 17400.
205000.
155300.
64200.ftf)
6800
35500
7220000
1S2O0.
li".
77600 2000UO.*
2101)00.
r.3d
*
*62 rn.
*7900.
2430.
321000,
72 to.
![Page 101: 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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/101.jpg)
- 92 -
S*I»MSMNOSMPMSM*MSMtuSMEU60EU<àOSMtuôoEUV»D6060TB00TBOYTBntDYOYOYHOHO
148620 • • 4.7149610 1400.149620 69000.150600 .150620 .151610 i151620 •152620 ,153620 .153630 i154620 ,154630154640155630 .155640156620156630156640157630157640)58640159640159650160640160650160660161650161660162660163660164660145670166670
<
•
> <
i t
» <
i i
F <
I 1
|
I
1
1
1
I
I
1
1
1
1
1
1.2100*400.
14200.20Ô.
» 2000.» 450.
> 1500*i «5,» 4200.> 48600», 3.0OUi 2000.
1.4i 2000., 205000.
2.8» 2000.• ?2.
.8. 600.• 60,• 2000.i 600.> 190.• 130.. 2700.• 63.• •
14.240.
Il
II
3000,
1500.••
250.*
«
90-•«
60.•
420.7.*
1200.
1200*2800*1900.
700.•
36300
68800.
41000
27
44
205000S3S0
126*700
107000
1113
116 30
![Page 102: 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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/102.jpg)
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](https://reader036.vdocuments.mx/reader036/viewer/2022081619/60f96cd1a236315f6367c6cc/html5/thumbnails/103.jpg)
So.
-1 IT-a -M6-»»% 95%«-II9-Q -120-g «i-121-g
76»
—121 — 4
-122-g
-122-gJ
-122-9
[»)-l23-g
-123-9I
- 1 2 3 - g
-124-g
- 1 2 4 - gSOd
-124-g
)-l28-g8.4*
- 1 2 5 - g2.S»
20KTm-l«8-gSSd
-126-g
I S *
-126-g
Lo-139-g
-140-gI li*
-140-g1 40k
-140-g33d
Nd
l27-(g)
-127- g17 d
ii%>&m - 1 2 7 - g
-127-g
97
- lU-(g)
-129-g
-I2t-(g)
-128-g
n-l2a-(g)S4«
-I29-*
m - 1 2 9 - «aod
-130-g
-ISO-gl2h
-130-g
* tS%i-ISI-(g)
- 1 3 1 - g8,0d
m-3l-g12 d
-132-g
-UH«)
-IÎ2-9
-142-g
-142-g19k
-142-g
-143-g33 k
-143-g14 d
-143-g
-144- «|280d
- l 44 - { 8 )I «.Ok
-IS3-(g)
-133- g2111
m-ISS-42,3d I 9,3d
-133-g
-151 - g
Tk
-169- g
-199-g
-ISO-g
f
-ISO-g
9,9 k
- 1 9 5 - 1
ME.
j»jj
Sm
99Bo
-134- (g I
-134-g
-134-gI 2.1»
-134-g
- 1 3 6 - g
2WI*w-136-g16 n 19.19(1
-133-g
, -133-g
- 1 3 6 - g113d
-136-g
-IST-(g)
- 1 3 7 - gI 30»
-137-g
IS.
-138-g - l39- (g l
-147-fI 2.7»
-147- g
m-148-g41 d I 9.4H
-148-0
-149-g|33h
-149-9
-150-9
-190- (g)
- 1 5 0 - g
•-4-H-fH"—hH--
—IS I— gI 28h
-151- g
-192-g
60
-BZ-(g)
-192-g
«5 -Ça.
-193-g - l64-fl6f l69
4H r~l69-(g )
-198-g
6!
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