measurement of neutron emission spectra and activation in li, be,c,al,fe,ta(d,n) reactions by in the...
TRANSCRIPT
Measurement of neutron emission spectra and activation in Li,
Be,C,Al,Fe,Ta(d,n) reactions by in the 20-40 MeV region
M.Baba, M.Hagiwara, T.Itoga, T.AokiCyclotron & Radioisotope Center, Tohoku University , Japan
M.SugimotoJapan Atomic Energy Research Institute, Tokai Establishment, Japan
T.Muroga,National Institute for Fusion Research, Toki, Japan
**** CONTENTS *******1. Introduction2. Apparatus & Experimental Methods
3. Results; Neutron spectra & Activation
4. Summary
1. INTRODUCTION
In IFMIF ・ Neutron spectrum extends beyond 50 MeV (High energy
tail)
・ Neutrons show very strong angular dependence ・ Beam intensity is as high as 250 mA
Design & maintenance of IFMIF require the data on ・ Energy-angular distribution of (d,n) neutrons; Li, accelerator structural elements ・ Production/ accumulation of radioactive nuclides 3H , 7Be, 22Na, 24Na etc
Experimental data were very few and discrepant
INTRODUCTION(2)
7 Li ( d,n) TTY; M. A. Lone et al. Nucl. Instrum. and Methods 143 (1977) 331-344
* Large discrepancies, Energy range is limited
In this study
1. Neutron spectrum from thick, thin targets of - Li, Be, C, Al, Fe, Ta - @ 25, 40 MeV - 0-110-deg. ・ Comparison with exp., calculations ・ Systematics vs mass 2. Radio-nuclide production - Li, Be, C, Al, Fe, (Ta) - 7Be, 22Na, 24Na, etc
2. Experimental ApparatusCyclotron & Radioisotope Center, Tohoku University (CYRIC)Performance of
K=110 AVF cyclotron•Protons 10-90
MeV•Deuterons 10-65
MeV•3He 20-170
MeV•4He 20-130
MeV・ Heavy Ions ・ Beam Chopper etc.
Layout of CYRIC
Automated-irradiation apparatusOnline-mass separator
Semiconductor Irradiation apparatus
Beam swinger
Flight path
Beam chopper
CYRIC TOF Line
Beam-swinger system
Beam-swinger & Well collimated TOF channel
Setup detectors at two locations
Vertical view of neutron course12
5cm
Target
1m
Beam Dump
1m 2.83m
30cm wide20cm high
Polyethylene
iron
5th Target Room TOF Room
Flight Path: 11mFlight Path:3.452m
Concrete
1m
30cm
Scattering Chamber
Beam Swinger
30cm
Bending Magnet
TOF MeasurementTOF Measurement
MCS
Copper Mesh(-500V)
3 parameter list mode・ 2-gain・ 2-flight path
Radio-nuclides production
After TOF measurement, γ-ray measurement with Ge detector
4-1. SETUP
0 1000 2000100
101
102
103
104
105
106
-ray energy (keV)
Cou
nts
7Be 477.6 keV
4-2. γ-ray spectrum
Ge detectorHV+4000V
Amp
MCA
Sample
γray
19 cm0 1000 2000
100
101
102
103
104
105
106
-ray energy (keV)
Coun
ts
7Be 477.6 keV
deuteron neutron spectrum meas.
TOF data processing
n- discrimination [channel]
Pul
se h
eigh
t [c
hann
el]
n- discrimination [channel]
Pul
se h
eigh
t [c
hann
el]
high-gain raw data low-gain raw data
n-eventn-event -event
-event
Derivation of neutron spectrum
1. n-γdiscrimination2. Bias setting ; ~ 0.6 MeV for high-gain, ~ 3.5 MeV for low-
gain3. TOF to energy spectrum
m0 : Rest mass of a neutron
I : Channel number of the eventsL : Flight pathc : Light velocity.
4. Absolute scale ; detector efficiency , solid-angle, current (SCINFUL-R code).5. Corrections for attenuation in target (air:LA150 ) just stopping length to avoid excessive correction
)(
)(1
1
1)(
2
20
20
2
iTc
L
c
xvcmcmmciE
n
nn
Radionuclide production (1)
n
i
tini
TT eQee
CR
mc
1
)( }{)1(
totalQRN
tI
NA
: decay constant (s-1), C : total counts of gamma-ray peak area, : peak efficiency,Tc : cooling time (s),
: branching ratio of gamma rays,Tm: counting time (s),
Qi : beam current (Coulomb) for irradiation time
interval Dt (s) [using Multi Channel Scaler : MCS]N : number of produced atoms in the target (atom),A : dps/(A·h)I : beam current (A)T : irradiation total time (h)
1) Reaction rate
2) Number of products
3) Activity
0 500 1000 1500100
101
102
103
104
105
Cou
lom
b/1
min
[*1
0-10 ]
channel/1 min
Beam fluctuation with MCS
Energy determination & attenuation correction
ItN
RNQ
d
4) Cross-section
Rdionuclide production (2)
1. Energy of each stack sample-TRIM code
0 5 10 15 20 250
10
20
30
40 dE/dx (deuteron in Li) Energy distribution (deuteron in Li)
Depth (mm)
Ene
rgy
(MeV
)
0 1 210-1
100
Depth (cm)
Att
enat
ion
fact
or
by Shen's emprical formula
1. Attenuation of sample- Shen’s empirical formula
3. Results & Discussion
1. Neutron spectrum; 0~110-deg. ・ Li, Be Ed= 25 MeV thick, thin (Li) Ed= 40 MeV thick, thin (Li) ・ C, Al, Fe, Cu, Ta, W Ed= 40 MeV thick
2. Radionuclide production Target: Li, C, Al, Fe, Ta, W Nuclides; 7Be, 22Na, 24Na,
0 10 20 30 40105
106
107
108
109
1010
1011
Present Ed=25MeV 0deg
M.A.Lone et al. Ed=23MeV 0deg
Neu
tron
Yie
ld [
MeV
-1・
sr-1・
C-1
]
Neutron Energy [MeV]
Comparison with Lone’s data natLi(d,xn) 0-deg for 25 MeV
0 10 20 30 40 50104
105
106
107
108
109
1010
1011
Neutron energy [MeV]
Neu
tron
yie
lds
[MeV
-1sr
-1C
-1]
natLi(d,xn) spectra
0-deg 5-deg 10-deg 15-deg 20-deg 25-deg 30-deg 40-deg 60-deg 90-deg
natLi(d,xn) Ed = 25 MeVThick lithium
0 10 20 30 40 50106
107
108
109
1010
1011
Neutron Energy [MeV]
Neu
tron
flu
x [#・
MeV
-1・
sr-1・
C-1
]
0-deg 10-deg 15-deg 20-deg 30-deg 45-deg 60-deg 90-deg 110-deg
0 10 20 30 40 50105
106
107
108
109
1010
Neutron Energy [MeV]
Neu
tron
flu
x [#
・M
eV-1・
sr-1・
C-1
]
0-deg 10-deg 15-deg 20-deg 30-deg 45-deg 60-deg 90-deg 110-deg
thick natLi(d,xn) for Ed= 40 MeV [7Li(d,n) Qvalue=+15.0 MeV]
thin natLi(d,xn) for Ed= 40 MeV [7Li(d,n) Qvalue=+15.0 MeV]
natLi(d,xn) Ed = 40 MeV Thick and thin lithium
0 10 20 30 40 50104
105
106
107
108
109
1010
1011
Neutron energy [MeV]
Neu
tro
n y
ield
s [M
eV-1sr
-1C
-1]
natLi(d,xn) spectra
0-deg 5-deg 10-deg 15-deg 20-deg 25-deg 30-deg 40-deg 60-deg 90-deg
natLi(d,xn) [7Li(d,n) Q 値 =+15.0
MeV]
0 10 20 30 40 50104
105
106
107
108
109
1010
1011
Neutron energy [MeV]
Neu
tro
n y
ield
s [M
eV-1sr
-1C
-1]
0-deg 5-deg 10-deg 15-deg 20-deg 25-deg 30-deg 40-deg 60-deg 90-deg
natBe(d,xn) [9Be(d,n) Q 値 =4.36 MeV]
Li; comparison with exp. & calculation
0 10 20 30 40 50106
107
108
109
1010
1011
Neutron Energy [MeV]
Neu
tron
flux
[#・
MeV
-1・
sr-1・
C-1
]
Present (0-deg) F.M. Mann et al McDeli McDeliciuos MCNPX
0 10 20 30 40 50106
107
108
109
1010
1011
Neutron Energy [MeV]
Neu
tron
flu
x [#
・M
eV-1・
sr-1・
C-1
]
Present (20-deg) F.M. Mann et al McDeli McDeliciuos MCNPX
Neutron yields
0 10 20 30 40109
1010
1011
1012
Deuteron Energy [MeV]
Neu
tron
Yie
ld [
#・sr
-1・
C-1
]
Forward ( = 0 deg)
Present Aoki et al. Daruga et al. Weaver et al. Goland et al. Amols et al. Nelson et al. Lone et al. Salmarsh et al. Johnson et al. Sugimoto et al. MCDeLicious cal. MCDeLi cal. MCNPX cal.
1010
1011
Neu
tron
Yie
ld [
#・C
-1]
Present Aoki et al. Lone et al. Johnson et al. Sugimoto et al. Mann et al. MCDeLicious cal. MCDeLi cal. MCNPX cal.
Total ( = 4)
4π-integrated
0 ゜ - differential
0 10 20 30 40105
106
107
108
109
1010
0-deg 5-deg 10-deg 15-deg 20-deg 30-deg 45-deg 60-deg 90-deg 110-deg
Neutron Energy (MeV)
Neu
tron
Flu
x (#
・M
eV-1・
C-1・
sr-1
)
Li(d,n) 25 MeV neutron spectra
0 10 20 30 400
0.2
0.4
0.6
0.8
1[109] EXP 0-deg Ext-Serber model Serber model
Neutron Energy (MeV)
Neu
tron
Flu
x (#
・M
eV-1・
C-1・
sr-1
)
7Li(d,n)8Be exitation level
7Li(d,n)8Be G.R.
Li(d,n) 25 MeV at 0 deg
D 25 MeV thin spectra: Serber / Advanced Serber model *
* H.Utsunomiya (MSU); Phys. Rev., C32 (1985) 32
0 10 20 30 40 500
1
2
3[109] EXP 0-deg Ext-Serber model Serber model
Neutron Energy (MeV)
Neu
tron F
lux
(#・M
eV-1・
C-1・
sr-1)
Li(d,n) 40 MeV at 0-degree
7Li(d,n)8Be G.R.
7Li(d,n)8Be exitation level
D 40 MeV thin spectra: Serber / Advanced Serber model
natC(d,xn) , 27Al(d,n) spectra
0 10 20 30 40 50105
106
107
108
109
1010
Neu
tron
yie
lds
[#・
MeV
-1・
sr-1・
C-1
]
Neutron energy [MeV]
0-deg 10-deg 15-deg 20-deg 30-deg 45-deg 60-deg 75-deg 90-deg 110-deg
0 10 20 30 40 50105
106
107
108
109
1010
Neu
tron
yie
lds
[#・
MeV
-1・
sr-1・
C-1
]
Neutron energy [MeV]
0-deg 10-deg 15-deg 20-deg 30-deg 45-deg 60-deg 75-deg 90-deg 110-deg
C A
l
Fe, Ta(d,n)
0 10 20 30 40 50102
103
104
105
106
107
108
109
1010
0 10 20 30 40 50102
103
104
105
106
107
108
109
1010
natTa(d,n)
Neu
tron F
lux [#/
(MeV
·sr·
C)]
Neutron energy [MeV]
natFe(d,n)
00 deg. 05 deg. 15 deg. 30 deg. 60 deg. 90 deg. 110 deg.
Fe, Ta(d,n): comparison
0 10 20 30 40104
105
106
107
108
109
1010
0 10 20 30 40102
103
104
105
106
107
108
109
1010
Meulders et al., Ed =33 MeV
Neu
tron
Flu
x [#
/(M
eV·s
r·C
)]
Neutron energy [MeV]
Meulders et al., Ed =50 MeV
present Ed = 40 MeV
Ta(d,n) at 0 degree
15 deg.
Neutron energy [MeV]
Line : Shin et al., Ed=33MeV, Cu(d,n)Symbol : present, Ed=40 MeV, Fe(d,n)
0 deg.
J. P. Meulders, et al., Phys. Med. Biol., 20, (1975) 235-243K. Shin, et al., Phys. Rev. C, 29, (1984) 1307-1316
0.5 1 5 10 5010-1
100
101
102
103
104
105
106
107
108
109
1010
1011
15 deg
Ta Fe C Al Li
Neu
tro
n F
lux
[#
/(MeV
·sr·C
)]
Neutron Energy [MeV]
0 deg.
Cross-section systematics vs mass
(d,n) @Ed=40MeVLi(d,n) :
largest yieldsC(d,n) :
yield is larger than heavy element
M. Hagiwara, et al., J. Nucl. Materials, 329-333, (2004) 218-222
M. Hagiwara, et al., J. Fusion Sci. Tech., in print
Spectrum mass-dependence
・ Spectrum becomes softer with mass
1 2 3 4 5
109
1010
Fe
C
Al
Ta
Neu
tro
n F
lux
[#
/(M
eV·s
r·C)]
Neutron Energy [MeV]
Li
M. Hagiwara, et al., J. Nucl. Materials, 329-333, (2004) 218-222
M. Hagiwara, et al., J. Fusion Sci. Tech., in print
Comparison with MCNPX; Fe, Ta
104
105
106
107
108
109
Fe, 60 deg.
104
105
106
107
108
109
Fe, 110 deg.
0 10 20 30 40 50104
105
106
107
108
109
MCNPX present exp.
Ta, 0 deg.
Neu
tron
Flu
x [#
/(M
eV·s
r·C
)]
0 10 20 30 40 50
Ta, 110 deg.
Neutron energy [MeV]0 10 20 30 40 50
104
105
106
107
108
109
Ta, 110 deg.
Fe, 0 deg.
Radionuclide production
0 10 20 30 40 500
20
40
60
80
100
Deuteron Energy (MeV)
Cros
s Sec
tion
(mb)
PresentIRACM XS fileB.Ja.Guzhovskij et al.O.N.Vysotskij et al.
0 10 20 30 40104
105
106
107
Deuteron Energy (MeV)
dps
μ・
A-1
・ho
ur-1
Presentdata with present XSU.Von Möllendorff et al.S.Mukhammedov et al.P.P.Dmitriev et al.IRACM calculation
natLi(d,x)7Be activation cross-section , natLi(d,x)7Be activity (TTY)
lithium (IFMIF target) Ed= 40, 38.6, 29.7, 28.2, 19.7, 17.7, 10, 7.05 MeVnatLi(d,x)7Be activation cross-section natLi(d,x)7Be activity (TTY)
natC(d,x)7Be
27Al(d,x)7Be
・ PHITScode・ other exps.
20 30 40 500
2
4
6
8
10
Deuteron Energy (MeV)C
ross
Sec
tion
(m
b)
PresentPHITS calc.
20 30 40 500
0.1
0.2
0.3
0.4
0.5
0.6
Deuteron Energy (MeV)
Cro
ss S
ecti
on (
mb)
PresentU.Martens et al.PHITS calc.
・ PHITS code (JQMD and GEM)
27Al(d,x)24Na
27Al(d,x)22Na
0 10 20 30 40 500
20
40
60
80
Deuteron Energy (MeV)C
ross
Sec
tion
(m
b)
PresentIAEA recomendS.Takacs et al.U.Martens et al.PHITS calc.
20 30 400
10
20
Deuteron Energy (MeV)
Cro
ss S
ecti
on (
mb)
PresentIAEA recomendS.Takacs et al.U.Martens et al.PHITS calc.
・ PHITS code・ Other Exps.・ Recommendation
・ PHITS code・ Other Exps.・ Recommendation
27Al(d,x)24Na activity (TTY)
27Al(d,x)22Na activity (TTY)
・ compare with IAEA data
Estimation
・ compare with IAEA
10 20 30 40104
105
106
107
108
109
1010
Deuteron Energy (MeV)
dpa・
A-1・
hour
-1
Al(d,x) 24Na Present estimationAl(d,x) 24Na Estimation with IAEA dataC(d,x)7Be Present estimationAl(d,x) 24Na Present TTYC(d,x)7Be Present TTY
20 30 40101
102
103
104
Deuteron Energy (MeV)
dpa・
A-1・
hour
-1Al(d,x) 22Na Present estimationAl(d,x) 22Na Estimation with IAEA dataAl(d,x) 7Be Present estimationAl(d,x) 22Na Present TTYAl(d,x) 7Be Present TTY
27Al(d,x)7Be activity (TTY)
natC(d,x)7Be activity (TTY)
Fe Activation cross-section (I)
natFe(d,x)51CrnatFe(d,x)52Mn
*TALYS is a nuclear reaction program using update code parameter created at NRG Petten.
0 10 20 30 40 5010-3
10-2
10-1
100
101
102
present 51Cr A. Hermanne et al. J. W. Clark et al. TALYS
Cro
ss s
ecto
n [m
b]
0 10 20 30 40 5010-3
10-2
10-1
100
101
102
present 52Mn A. Hermanne et al. Zhao Wenrong et al. TALYS
Deuteron energy [MeV]
Fe Activation cross-section (II)
natFe(d,x)56Co
natFe(d,x)57ConatFe(d,x)58Co
0 10 20 30 40 50100
101
102
present 56Co J. W. Clark et al. Zhao Wenrong et al. P. Jung IAEA recommend TALYS
Cro
ss s
ecti
on [
mb]
0 10 20 30 40 50
present 57Co A. Hermanne et al. J. W. Clark et al. S. Takacs et al. TALYS
Deuteron energy [MeV]
0 10 20 30 40100
101
102 present 58Co J. W. Clark et al. Zhao Wenrong et al. TALYS
Summary & Future
1.Measurements of neutron spectrum for (d,nx) reactions 1) Li , Be, C , Al , Fe , Cu , Ta - Ed=40, 25 MeV, - 0 ~ 110 deg
- Energy spectrum shape was clarified, high energy tail 2) Systematics vs target mass
2. Production yields of radio-nuclides via (d,x) reaction 1) Li , C , Al , Fe , Cu , Ta
Provided data base for IFMIF optimization & post irradiation analysis
Future program: Deuteron induced reactions & neutron induced reactions
* CDCC (Continuum-discritized coupled-channel) model; BRC * Extended Serber model ?
CYRIC new neutron course (@TR3 extension)
Ep = 50 MeV, E = 2 MeV mono-E n flux 106 n/cm2sA
beam dump7Li(p,n)
74 cm
3~100 Ap beam
• Software error rate• n-induced activation, reaction few-body reactions, etc.
0 20 40 60 800
1
2
Neutron Energy [MeV]
Neu
tron
yei
ld [
sr-1
MeV
-1C
-1] [× 109]
En=75 [MeV] En=65 [MeV] En=55 [MeV]
Reference [1] IFMIF CDA TEAM, IFMIF Conceptual Design Activity Final Report edited by Marcello Martone, Report 96.11,
Enea, Dipartimento Energia, Frascati (1996) [2] M.A.Lone et al., Nucl. Instrum. Methods, 143 (1977) 331 [3] M. Baba, T. Aoki, M. Hagiwara et al., J. Nucl. Materials 307-311 (2002) 1715-1718. [4] T. Aoki, M. Hagiwara, M. Baba et al., J. Nucl. Sci. and Tech. to be published [5] A.Terakawa et al., Nucl. Instrum. Methods A 491 (2002) 419. [6] M. Baba, H. Wakabayashi, M. Ishikawa, T. Ito and N. Hirakawa, J. Nucl. Sci. Technol., 27(No.7), 601 (1990) [7] T. Aoki , M. Baba, S. Yonai, N. Kawata, M. Hagiwara, T. Miura, T. Nakamura, Nucl. Sci. Eng., in print [8] J. F. Ziegler, J. P, Biersack, U. Littmark, Pergamon Press, New York (1984). [9] S.Meigo Nucl. Instrum. Methods in Physics Research A 401 (1997) 365 [10] M. B. Chadwick, P. G. Young et al., Nucl. Sci. Eng. 131, 293, 1999 [11] W.Nelson, H.Hirayama, D.W.O.Rogers, “The EGS4 Code System” SLAC-265, Stanford University, Stanford
(1985) [12] W. Q. Shen, B. Wang, J. Feng, W. L. Zhan, Y. T. Zhu and E. P. Feng, Nucl. Phys. A, 491, 130 (1989) [13] J. P. Meulders et al. Phys. Med. Biol., 20, p.235, 1975 [14] Z. Radivojevic, A. Honkanen, J. Aysto, V. Lyapin, V. Rubchenya, W. H. Trzaska, D. Vakhtin and G. Walter, Nucl.
Instr. and Meth. B., 183, p.212, 2001 [15] S.P.Simakov, U.Fisher, U.von Mllendorf, I.Schmuck, A.Yu.Konobeev, Yu. A. Korvin, P.Pereslavtsev; J. Nucl.
Materials, 307-311 1710-1714 (2002) [16] S. Takacs, F. Szelecsenyi, F. Tarkanyi, M. Sonck, A. Hermanne, Yu. Shubin, A. Dityuk, M.G. Mustafa, Z.
Youxiang, Nucl. Instr. and Meth. B., 174 (2001) 235-258 [17] U. Martens and G. W. Schweimer, Zeitschrift für Physics 233 (1970) 170 [18] IAEA, Charged-particle cross section database for medical radioisotope production http://www-nds.iaea.org/medical/ [19] H. Iwase, K. Niita, T. Nakamura, J. Nucl. Sci. Tech. 39, No.11, 1142 (2002)
Differential TTY of natC: 12C(p,n), 13C(p,n)
0 10 20 30 40 50102
103
104
105
106
107
108
109
1010
1011
1012
1013
1014
Neutron energy [MeV]
Neu
tro
n y
ield
s [M
eV-1sr
-1C
-1]
Points :PresentSolid line:LA150
0-deg*1000 15-deg*100 30-deg*10 45-deg 60-deg*0.1 90-deg*0.01
1.E+02
1.E+03
1.E+04
1.E+05
1.E+06
1.E+07
1.E+08
1.E+09
1.E+10
1.E+11
0 10 20 30 40 50 60 70
Energy [MeV]
Neut
ron
Yie
ls [
neut
ron/
MeV
/sr/
μC]
LA150_0 deg.× 100LA150_30 deg.× 10LA150_60 deg.× 1 LA150_90 deg.× 0.1LA150_110 deg.× 0.010 deg.× 10030 deg.× 1060 deg.90 deg.× 0.1110 deg.× 0.01
Ep=50 MeV
Ep=70 MeV
・ Scarcity of experimental data for whole spectrum
“ Measurement of full energy range ”・ Target: 30-mm-diam x full stop thickness 0-110 deg.,・ Efficiency; SCINFUL-R Correction; Attenuation in target, air・ Comparison with LA-150
3. Differential TTY (Thick target neutron yield)
'/exp
/
00
0
002
02
dtdtdtdEEN
dEd
dtdtdEEdN
dEd
EYd
t
t
nonel
T
t
TTY: W(p,n)
0 10 20 30 40 50102
103
104
105
106
107
108
109
1010
1011
1012
1013
1014
Neutron energy [MeV]
Neu
tron
yie
lds
[MeV
-1sr
-1C
-1]
natW(p,xn) spectraPoints :PresentSolid line:LA150
0-deg*1000 15-deg*100 30-deg*10 45-deg 60-deg*0.1 90-deg*0.01
1.E+04
1.E+05
1.E+06
1.E+07
1.E+08
1.E+09
1.E+10
1.E+11
1.E+12
1.E+13
0 10 20 30 40 50 60 70
Energy [MeV]
Neut
ron
Yiel
s [n
eutr
on/M
eV/s
r/μ
C]
0 × 100度30 × 10度60 × 1度90 × 0.1度110 × 0.01度LA150_0 × 100度LA150_30 × 10度LA150_60 × 1 度LA150_90 × 0.1度LA150_110 × 0.01度
Ep=50 MeV Ep=70 MeV
0.1
1
10
100
0 10 20 30 40 50 60 70 80 90
Neutron energy [MeV]
Cro
ss s
ecti
on [
mb]
14N(n,2n)13NPHITSINC/ GEMEXFOR dataENDF/ B- VI
0.1
1
10
100
0 10 20 30 40 50 60 70 80 90
Neutron energy [MeV]
Cross s
ectio
n [
mb]
16O(n,2n)15OPHITSINC/ GEMEXFOR dataENDF/ B- VI
Neutron-induced activation X-section
1. はじめに (4)
目 的1. IFMIF 加速器構成材核種の( d,n) 中性子スペクトルの測定 ・ Li, C, Al, (Fe, Cu) ・ Ed=25- 40 MeV, 0 – 90 ゜ ・厚いターゲット,薄いターゲット ・スペクトルの全範囲の測定
2. IFMIF 加速器構成材核種と重陽子反応による放射性核種生成 ・ Li, C, Al, (Fe, Cu) ・厚いターゲット,薄いターゲット ・スタックターゲット法による励起関数の導出 ・ 7Be, (3H), , 24Na, 24Na
3. 実験
1.東北大学サイクロトロン ・第五ターゲット室, ・ビームチョッパー ・ビームスウィンガー+飛行管室; 高いエネルギー分解能, S/N 比,広いスペクト
ル範囲
2. スタックターゲットの利用 ・厚いターゲットと薄いターゲットの対する同時測定 ・中性子スペクトル,放射化の同時測定
INTRODUCTION(2)
n+28Si (LA150)