ENTRY 33033 20120120 31583303300000001
SUBENT 33033001 20120120 31583303300100001
BIB 14 232 3303300100002
TITLE Measurement of the neutron capture cross-section of 3303300100003
232-Th using the neutron activation technique 3303300100004
AUTHOR (H.Naik, P.M.Prajapati, S.V.Surayanarayana, 3303300100005
K.C.Jagadeesan, S.V.Thakare, D.Raj, V.K.Mulik, 3303300100006
B.S.Sivashankar, B.K.Nayak, S.C.Sharma, S.Mukherjee, 3303300100007
Sarbjit Singh, A.Goswami, S.Ganesan, V.K.Manchanda) 3303300100008
INSTITUTE (3INDTRM,3INDBDA,3INDPOO) 3303300100009
(3INDIND) Manipal University, Manipal 3303300100010
REFERENCE (J,EPJ/A,47,51,2011) 3303300100011
FACILITY (VDG,3INDTRM) BARC-TIFR pelletron facility at TIFR 3303300100012
SAMPLE The samples used for irradiation were natural 232-Th 3303300100013
metal foil and natural In metal foil, which were 3303300100014
wrapped separately with 0.025 mm thick aluminum foil 3303300100015
to prevent contamination from one to the other. 3303300100016
The size of 232-Th metal foil was 1.0 cm**2 with 3303300100017
thickness of 29.3 mg/cm**2, whereas indium metal foil 3303300100018
is also of same size with thickness of 2.6 mg/cm**2. 3303300100019
DETECTOR (HPGE) The gamma-rays of fission/reaction products 3303300100020
from the irradiated Th and In samples were counted 3303300100021
in an energy and efficiency calibrated 80 c.c. 3303300100022
HPGe detector coupled to a PC-based 4K channel analyzer3303300100023
METHOD (ACTIV,GSPEC) The 232Th(n,g) reaction cross-section 3303300100024
at average neutron energy of 3.7 MeV and 9.85 MeV has 3303300100025
been determined for the first time using activation 3303300100026
and off-line gamma-ray spectrometric technique. 3303300100027
The observed photo-peak activity (Aobs) of gamma-lines 3303300100028
was obtained using PHAST peak fitting programme. 3303300100029
INC-SOURCE (P-LI7) The neutron beam was obtained from the 3303300100030
7-Li(p,n) reaction by using the proton beam main 3303300100031
line at 6 m above the analyzing magnet of the 3303300100032
Pelletron facility to utilize the maximum proton 3303300100033
current from the accelerator. 3303300100034
INC-SPECT 7Li(p,n) at Ep = 5.6 MeV calculated using the results 3303300100035
of Meadows and Smith (Fig.5) 3303300100036
-------------------------- 3303300100037
En Neutron Flux 3303300100038
MEV mb/Sr-MeV 3303300100039
-------------------------- 3303300100040
0.1 7.79E-04 3303300100041
0.2 0.0014 3303300100042
0.3 0.00189 3303300100043
0.4 0.00225 3303300100044
0.5 0.0025 3303300100045
0.6 0.00267 3303300100046
0.7 0.00275 3303300100047
0.8 0.00276 3303300100048
0.9 0.00272 3303300100049
1 0.00263 3303300100050
1.1 0.0025 3303300100051
1.2 0.00235 3303300100052
1.3 0.00217 3303300100053
1.4 0.00198 3303300100054
1.5 0.00178 3303300100055
1.6 0.00157 3303300100056
1.7 0.00136 3303300100057
1.8 0.00114 3303300100058
1.9 9.38E-04 3303300100059
2 7.38E-04 3303300100060
2.1 5.46E-04 3303300100061
2.2 3.63E-04 3303300100062
2.3 1.90E-04 3303300100063
2.4 2.04E-10 3303300100064
2.5 8.07E-09 3303300100065
2.6 2.14E-07 3303300100066
2.7 3.82E-06 3303300100067
2.8 4.56E-05 3303300100068
2.9 3.65E-04 3303300100069
3 0.00196 3303300100070
3.1 0.00705 3303300100071
3.2 0.01701 3303300100072
3.3 0.02777 3303300100073
3.4 0.0323 3303300100074
3.5 0.03531 3303300100075
3.6 0.05984 3303300100076
3.7 0.12234 3303300100077
3.8 0.19292 3303300100078
3.9 0.20829 3303300100079
4 0.15118 3303300100080
4.1 0.07358 3303300100081
4.2 0.02401 3303300100082
4.3 0.00525 3303300100083
4.4 7.70E-04 3303300100084
4.5 7.57E-05 3303300100085
4.6 4.98E-06 3303300100086
4.7 2.20E-07 3303300100087
4.8 6.51E-09 3303300100088
4.9 1.29E-10 3303300100089
5 1.72E-12 3303300100090
5.1 1.53E-14 3303300100091
5.2 9.16E-17 3303300100092
5.3 3.67E-19 3303300100093
5.4 9.85E-22 3303300100094
5.5 1.77E-24 3303300100095
5.6 2.14E-27 3303300100096
-------------------------- 3303300100097
7Li(p,n) at Ep = 12 MeV calculated using the results 3303300100098
of Ep=10 MeV by Poppe (Fig.6) 3303300100099
-------------------------- 3303300100100
En Neutron Flux 3303300100101
MeV mb/Sr-MeV 3303300100102
-------------------------- 3303300100103
5.228 4.41928 3303300100104
5.278 5.04291 3303300100105
5.328 6.01152 3303300100106
5.378 7.55317 3303300100107
5.428 9.6155 3303300100108
5.478 11.48641 3303300100109
5.528 12.35986 3303300100110
5.578 11.64606 3303300100111
5.628 9.29659 3303300100112
5.678 5.64977 3303300100113
5.728 2.69334 3303300100114
5.778 1.59589 3303300100115
5.828 1.61459 3303300100116
5.878 1.86877 3303300100117
5.928 1.64885 3303300100118
5.978 1.21338 3303300100119
6.028 1.02771 3303300100120
6.078 1.01758 3303300100121
6.128 0.98905 3303300100122
6.178 0.90555 3303300100123
6.228 0.81651 3303300100124
6.278 0.76498 3303300100125
6.328 0.74102 3303300100126
6.378 0.71093 3303300100127
6.428 0.66059 3303300100128
6.478 0.62557 3303300100129
6.528 0.62654 3303300100130
6.578 0.62931 3303300100131
6.628 0.59609 3303300100132
6.678 0.53383 3303300100133
6.728 0.47473 3303300100134
6.778 0.44115 3303300100135
6.828 0.42253 3303300100136
6.878 0.40167 3303300100137
6.928 0.37026 3303300100138
6.978 0.34264 3303300100139
7.028 0.32534 3303300100140
7.078 0.31659 3303300100141
7.128 0.31049 3303300100142
7.178 0.29162 3303300100143
7.228 0.2498 3303300100144
7.278 0.21012 3303300100145
7.328 0.20051 3303300100146
7.378 0.20467 3303300100147
7.428 0.19287 3303300100148
7.478 0.15854 3303300100149
7.528 0.12748 3303300100150
7.578 0.12762 3303300100151
7.628 0.15781 3303300100152
7.678 0.16381 3303300100153
7.728 0.13334 3303300100154
7.778 0.09563 3303300100155
7.828 0.06795 3303300100156
7.878 0.04929 3303300100157
7.928 0.03749 3303300100158
7.978 0.03106 3303300100159
8.028 0.02881 3303300100160
8.078 0.02955 3303300100161
8.128 0.0322 3303300100162
8.178 0.03599 3303300100163
8.228 0.04029 3303300100164
8.278 0.0443 3303300100165
8.328 0.04673 3303300100166
8.378 0.04623 3303300100167
8.428 0.04142 3303300100168
8.478 0.03094 3303300100169
8.528 0.01527 3303300100170
8.578 0.01137 3303300100171
8.628 0.0303 3303300100172
8.678 0.05288 3303300100173
8.778 0.05851 3303300100174
8.828 0.04877 3303300100175
8.878 0.03774 3303300100176
8.928 0.02765 3303300100177
8.978 0.01968 3303300100178
9.028 0.01494 3303300100179
9.078 0.01457 3303300100180
9.128 0.0197 3303300100181
9.178 0.03147 3303300100182
9.228 0.05186 3303300100183
9.278 0.08576 3303300100184
9.328 0.12897 3303300100185
9.378 0.15814 3303300100186
9.428 0.14774 3303300100187
9.478 0.13522 3303300100188
9.528 0.45942 3303300100189
9.578 1.48469 3303300100190
9.628 2.91008 3303300100191
9.678 4.57921 3303300100192
9.728 6.12017 3303300100193
9.778 6.45023 3303300100194
9.828 5.31394 3303300100195
9.878 3.47149 3303300100196
9.928 2.39912 3303300100197
9.978 2.85879 3303300100198
10.028 2.529 3303300100199
10.078 5.1848 3303300100200
10.128 12.08801 3303300100201
10.178 13.36977 3303300100202
10.228 11.93188 3303300100203
10.278 9.48661 3303300100204
10.328 6.7653 3303300100205
10.378 4.03077 3303300100206
10.428 1.17284 3303300100207
10.478 0.06397 3303300100208
10.528 -0.03379 3303300100209
10.578 0.05033 3303300100210
10.628 0.02146 3303300100211
REL-REF (R,,J.Blachot,J,NDS,104,967,2005) 115mIn decay data 3303300100212
(R,,B.Singh+,J,NDS,105,109,2005) 231Th decay data 3303300100213
(R,,J.W.Meadows+,R,ANL-7983,1972) 3303300100214
For calc. of 7Li(p,n) neutron spectrum at Ep=5.6 MeV 3303300100215
(R,,C.H.Poppe+,J,PR/C,14,438,1976) 3303300100216
For calc. of 7Li(p,n) neutron spectrum at Ep=12 MeV 3303300100217
ERR-ANALYS (ERR-T) The uncertainties associated to the measured 3303300100218
cross-sections come from the combination of two 3303300100219
experimental data sets. 3303300100220
This overall uncertainty is the quadratic sum of both 3303300100221
statistical uncertainty and systematic uncertainties 3303300100222
in: 3303300100223
(ERR-1) Neutron flux estimation (~4%) 3303300100224
(ERR-2) Irradiation time (~2%) 3303300100225
(ERR-3) Detection efficiency calibration (~3%) 3303300100226
(ERR-4) Half-life of the fission products and 3303300100227
the gamma-ray abundances (~2%). 3303300100228
(ERR-SYS) The total systematic error (~6%) 3303300100229
STATUS (APRVD) Entry approved by Dr. H. Naik 3303300100230
HISTORY (20110505C) Compiled by Mr.Paresh Prajapati and 3303300100231
Dr.S.Mukherjee, The M.S.University of Baroda, Vadodara3303300100232
(20110609A) On. Finalized. 3303300100233
(20120120A) NDS(VZ): REL-REF: ND/B->NDS 3303300100234
ENDBIB 232 0 3303300100235
COMMON 5 3 3303300100236
ERR-1 ERR-2 ERR-3 ERR-4 ERR-SYS 3303300100237
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3303300100238
4. 2. 3. 2. 6. 3303300100239
ENDCOMMON 3 0 3303300100240
ENDSUBENT 239 0 3303300199999
SUBENT 33033002 20120120 31583303300200001
BIB 5 7 3303300200002
REACTION (90-TH-232(N,G)90-TH-233,,SIG,,SPA) 3303300200003
DECAY-DATA (91-PA-233,26.975D,DG,311.9,0.384) 3303300200004
REL-REF (R,,E.Browne,J,NDS,93,763,2001) 233Th,233Pa decay data 3303300200005
(R,,B.Browne+,B,BROWNE,,1986) 233Th,233Pa decay data 3303300200006
STATUS (TABLE) Text (p5) of Eur.Phys.J.A47(2011)51. 3303300200007
(Values were truncated by author.) 3303300200008
HISTORY (20120120A) NDS(VZ): REL-REF: ND/B->NDS 3303300200009
ENDBIB 7 0 3303300200010
NOCOMMON 0 0 3303300200011
DATA 4 2 3303300200012
EN EN-ERR DATA ERR-T 3303300200013
MEV MEV MB MB 3303300200014
3.7 0.3 16.18 0.87 3303300200015
9.85 0.38 2.18 0.12 3303300200016
ENDDATA 4 0 3303300200017
ENDSUBENT 16 0 3303300299999
SUBENT 33033003 20110609 31513303300300001
BIB 3 24 3303300300002
REACTION (90-TH-232(N,G)90-TH-233,,SIG) 3303300300003
CORRECTION The contribution to the neutron flux from the tail 3303300300004
region is 4% and 49% at the proton energy of 5.6 MeV 3303300300005
and 12.0 MeV, respectively. 3303300300006
In view of this, the contribution from the tail region 3303300300007
to the 232-Th(n,g) reaction has been estimated using 3303300300008
the ENDF/B-VII, JENDL-4.0 and JEFF-3.1 by folding the 3303300300009
cross-sections with neutron flux distributions coded 3303300300010
under INC-SPECT. 3303300300011
The contributions 232-Th(n,g) to the reaction from the 3303300300012
above evaluation at Ep = 5.6 MeV are 5.34, 5.57 and 3303300300013
5.03 mb from ENDF/B-VII, JENDL-4.0 and JEFF-3.1 3303300300014
respectively. 3303300300015
Similarly at Ep = 12 MeV, 232-Th(n,g) the reaction 3303300300016
cross-sections from the above evaluation are 0.798 3303300300017
and 0.876mb from ENDF/B-VII and JENDL-4.0. 3303300300018
The actual value of the 232-Th(n, g) reaction cross- 3303300300019
section due to the neutrons from the main peak of the 3303300300020
n0 and n1 groups of the neutron spectrum is obtained 3303300300021
after subtracting the average cross-section due to 3303300300022
neutrons from the tail region from the before- 3303300300023
mentioned experimental data. 3303300300024
STATUS (TABLE) Table 2 of Eur.Phys.J.A47(2011)51 3303300300025
(DEP,33033002) Spectrum averaged cross-section 3303300300026
ENDBIB 24 0 3303300300027
NOCOMMON 0 0 3303300300028
DATA 4 2 3303300300029
EN EN-ERR DATA ERR-T 3303300300030
MEV MEV MB MB 3303300300031
3.7 0.3 10.9 0.9 3303300300032
9.85 0.38 1.35 0.12 3303300300033
ENDDATA 4 0 3303300300034
ENDSUBENT 33 0 3303300399999
SUBENT 33033004 20110609 31513303300400001
BIB 3 3 3303300400002
REACTION (90-TH-232(N,2N)90-TH-231,,SIG) 3303300400003
DECAY-DATA (90-TH-231,25.52HR,DG,84.2,0.066) 3303300400004
STATUS (TABLE) Table 2 of Eur.Phys.J.A47(2011)51 3303300400005
ENDBIB 3 0 3303300400006
NOCOMMON 0 0 3303300400007
DATA 4 1 3303300400008
EN EN-ERR DATA ERR-T 3303300400009
MEV MEV MB MB 3303300400010
9.85 0.38 1722. 76. 3303300400011
ENDDATA 3 0 3303300400012
ENDSUBENT 11 0 3303300499999
ENDENTRY 4 0 3303399999999