ENTRY 33040 20120711 31563304000000001 SUBENT 33040001 20120711 31563304000100001 BIB 14 50 3304000100002 TITLE Measurement of the neutron capture cross-sections of 3304000100003 232-Th at 5.9 MeV and 15.5 MeV 3304000100004 AUTHOR (P.M.Prajapati, H.Naik, S.V.Suryanarayana, 3304000100005 S.Mukherjee, K.C.Jagadeesan, S.C.Sharma, S.V.Thakre, 3304000100006 K.K.Rasheed, S.Ganesan, A.Goswami) 3304000100007 INSTITUTE (3INDTRM,3INDBDA) 3304000100008 REFERENCE (J,EPJ/A,48,35,2012) 3304000100009 FACILITY (VDG,3INDTRM) BARC-TIFR Pelletron at TIFR, Mumbai 3304000100010 SAMPLE The samples used for irradiation were natural 232-Th 3304000100011 metal foil (0.285 g) and natural In metal foil 3304000100012 (0.183 g) wrapped separately with 0.025 mm thick 3304000100013 aluminum foil to prevent contamination from one to 3304000100014 the other. 3304000100015 The sizes of 232-Th and 115-In metal foils were 3304000100016 1.0 cm2. 3304000100017 DETECTOR (HPGE) The gamma-rays of fission/reaction products 3304000100018 from the irradiated Th and In samples were counted 3304000100019 in an energy and efficiency calibrated 80 c.c. HPGe 3304000100020 detector coupled to a PC-based 4K channel analyzer 3304000100021 METHOD (ACTIV,GSPEC) The 232-Th(n,g) reaction cross-section 3304000100022 at average neutron energy of 5.9 MeV and 15.5 MeV has 3304000100023 been determined for the first time using activation 3304000100024 and off-line gamma-ray spectrometric technique. 3304000100025 The sample were irradiated for 5 hrs to 15 hrs. 3304000100026 The samples were cooled for 2 hrs after irradiation. 3304000100027 INC-SOURCE (P-LI7) The neutron beam was obtained from the 3304000100028 7-Li(p,n) reaction by using the proton beam main line 3304000100029 at 6 m above the analyzing magnet of the Pelletron 3304000100030 facility to utilize the maximum proton current from 3304000100031 the accelerator. 3304000100032 ANALYSIS The observed photo-peak activity (Aobs) of gamma-lines 3304000100033 was obtained using PHAST peak fitting programme. 3304000100034 REL-REF (R,,J.Blachot,J,NDS,104,967,2005) In-115m decay data 3304000100035 (R,,B.Singh+,J,NDS,105,109,2005) Th-231 decay data 3304000100036 (R,,E.Browne,J,NDS,93,763,2001)Th-233,Pa-233 decay data3304000100037 (R,,E.Browne+,B,BROWNE,,1986) Th-233,Pa-233 decay data3304000100038 ERR-ANALYS (ERR-T) The uncertainties associated to the measured 3304000100039 cross-sections come from the combination of two 3304000100040 experimental data sets. 3304000100041 This overall uncertainty is the quadratic sum of both 3304000100042 statistical and systematic errors. 3304000100043 (ERR-1) Neutron flux estimation (~6%) 3304000100044 (ERR-2) Irradiation time (~2%) 3304000100045 (ERR-3) Detection efficiency calibration (~3%) 3304000100046 (ERR-4) Half-life of the fission products and 3304000100047 the gamma-ray abundances (~2%) 3304000100048 (ERR-SYS) Total systematic error (~6%) 3304000100049 STATUS (APRVD) Entry approved by P.M. Prajapati 3304000100050 HISTORY (20120617C) Paresh Prajapati and S.Mukherjee 3304000100051 (20120711A) On. Finalized. CRITIQUE to 003 and 005. 3304000100052 ENDBIB 50 0 3304000100053 COMMON 5 3 3304000100054 ERR-1 ERR-2 ERR-3 ERR-4 ERR-SYS 3304000100055 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3304000100056 6. 2. 3. 2. 6. 3304000100057 ENDCOMMON 3 0 3304000100058 ENDSUBENT 57 0 3304000199999 SUBENT 33040002 20120711 31563304000200001 BIB 3 3 3304000200002 REACTION (90-TH-232(N,G)90-TH-233,,SIG,,SPA) 3304000200003 DECAY-DATA (90-TH-233,21.83MIN,DG,86.5,0.027) 3304000200004 STATUS (TABLE) Table 2 of Eur.Phys.J.A48(2012)35 3304000200005 ENDBIB 3 0 3304000200006 NOCOMMON 0 0 3304000200007 DATA 3 2 3304000200008 EN-DUMMY DATA ERR-T 3304000200009 MEV MB MB 3304000200010 5.9 6.47 0.11 3304000200011 15.5 2.35 0.12 3304000200012 ENDDATA 4 0 3304000200013 ENDSUBENT 12 0 3304000299999 SUBENT 33040003 20120711 31563304000300001 BIB 6 20 3304000300002 REACTION (90-TH-232(N,G)90-TH-233,,SIG) 3304000300003 DECAY-DATA (90-TH-233,21.83MIN,DG,86.5,0.027) 3304000300004 MISC-COL (MISC) Subtracted cross sections 3304000300005 CORRECTION The contribution from the tail region has been 3304000300006 estimated using the ENDF/B-VII, JENDL-4.0 and 3304000300007 JEFF-3.1 by folding the cross-sections with neutron 3304000300008 flux distributions. 3304000300009 The actual value due to the neutrons from the main 3304000300010 peak of the n0 and n1 groups of the neutron spectrum 3304000300011 is obtained after subtracting the average cross- 3304000300012 section due to neutrons from the tail region from the 3304000300013 before-mentioned experimental data. 3304000300014 CRITIQUE N.Otsuka (2012-07-11): 3304000300015 The correction made by the authors 3304000300016 sig=spa-tail 3304000300017 is suspicious. No clear explanation from the authors. 3304000300018 STATUS (TABLE) Table 2 of Eur.Phys.J.A48(2012)35 3304000300019 (DEP,33040002) Spectrum averaged cross-section 3304000300020 (DEP,33040006) Neutron spectrum at 7.8 MeV 3304000300021 (DEP,33040007) Neutron spectrum at 18 MeV 3304000300022 ENDBIB 20 0 3304000300023 NOCOMMON 0 0 3304000300024 DATA 6 2 3304000300025 EN EN-RSL DATA ERR-T MISC MISC-ERR 3304000300026 MEV MEV MB MB MB MB 3304000300027 5.9 0.6 1.13 0.21 5.36 0.18 3304000300028 15.5 0.7 0.78 0.18 1.57 0.14 3304000300029 ENDDATA 4 0 3304000300030 ENDSUBENT 29 0 3304000399999 SUBENT 33040004 20120711 31563304000400001 BIB 3 3 3304000400002 REACTION (90-TH-232(N,2N)90-TH-231,,SIG,,SPA) 3304000400003 DECAY-DATA (90-TH-231,25.52HR,DG,84.2,0.066) 3304000400004 STATUS (TABLE) Table 2 of Eur.Phys.J.A48(2012)35 3304000400005 ENDBIB 3 0 3304000400006 NOCOMMON 0 0 3304000400007 DATA 3 1 3304000400008 EN-DUMMY DATA ERR-T 3304000400009 MEV MB MB 3304000400010 15.5 1680. 103. 3304000400011 ENDDATA 3 0 3304000400012 ENDSUBENT 11 0 3304000499999 SUBENT 33040005 20120711 31563304000500001 BIB 6 20 3304000500002 REACTION (90-TH-232(N,2N)90-TH-231,,SIG) 3304000500003 DECAY-DATA (90-TH-231,25.52HR,DG,84.2,0.066) 3304000500004 MISC-COL (MISC) Subtracted cross sections 3304000500005 CORRECTION The contribution from the tail region has been 3304000500006 estimated using the ENDF/B-VII, JENDL-4.0 and 3304000500007 JEFF-3.1 by folding the cross-sections with neutron 3304000500008 flux distributions. 3304000500009 The actual value due to the neutrons from the main 3304000500010 peak of the n0 and n1 groups of the neutron spectrum 3304000500011 is obtained after subtracting the average cross- 3304000500012 section due to neutrons from the tail region from the 3304000500013 before-mentioned experimental data. 3304000500014 CRITIQUE N.Otsuka (2012-07-11): 3304000500015 The correction made by the the authors 3304000500016 sig=spa-tail 3304000500017 is suspicious. No clear explanation from the authors. 3304000500018 STATUS (TABLE) Table 2 of Eur.Phys.J.A48(2012)35 3304000500019 (DEP,33040003) Spectrum averaged cross-section 3304000500020 (DEP,33040006) Neutron spectrum at 7.8 MeV 3304000500021 (DEP,33040007) Neutron spectrum at 18 MeV 3304000500022 ENDBIB 20 0 3304000500023 NOCOMMON 0 0 3304000500024 DATA 6 1 3304000500025 EN EN-RSL DATA ERR-T MISC MISC-ERR 3304000500026 MEV MEV MB MB MB MB 3304000500027 15.5 0.7 933. 109. 747. 3. 3304000500028 ENDDATA 3 0 3304000500029 ENDSUBENT 28 0 3304000599999 SUBENT 33040006 20120617 31563304000600001 BIB 4 4 3304000600002 REACTION (3-LI-7(P,N)4-BE-7,,DA/DE,,MSC,CALC) 3304000600003 ANALYSIS Calculated using the results of C.H.Poppe at al. 3304000600004 REL-REF (R,D0038001,C.H.Poppe+,J,PR/C,14,438,1976) 3304000600005 STATUS (TABLE) Data received from P.M.Prajapati 3304000600006 ENDBIB 4 0 3304000600007 COMMON 1 3 3304000600008 EN 3304000600009 MEV 3304000600010 7.8 3304000600011 ENDCOMMON 3 0 3304000600012 DATA 2 110 3304000600013 E DATA 3304000600014 MEV MB/SR/MEV 3304000600015 0.978 2.5616 3304000600016 1.028 2.8348 3304000600017 1.078 2.2348 3304000600018 1.128 3.8561 3304000600019 1.178 4.8450 3304000600020 1.228 6.1679 3304000600021 1.278 7.3680 3304000600022 1.328 7.9283 3304000600023 1.378 7.4704 3304000600024 1.428 5.9633 3304000600025 1.478 3.6241 3304000600026 1.528 3.5258 3304000600027 1.578 2.0892 3304000600028 1.628 2.1137 3304000600029 1.678 2.4464 3304000600030 1.728 2.1585 3304000600031 1.778 1.5884 3304000600032 1.828 1.3454 3304000600033 1.878 1.3321 3304000600034 1.928 1.2948 3304000600035 1.978 1.1855 3304000600036 2.028 1.0689 3304000600037 2.078 1.0014 3304000600038 2.128 0.9701 3304000600039 2.178 0.9307 3304000600040 2.228 0.8648 3304000600041 2.278 0.8189 3304000600042 2.328 0.8202 3304000600043 2.378 0.8238 3304000600044 2.428 0.7803 3304000600045 2.478 0.6988 3304000600046 2.528 0.6215 3304000600047 2.578 0.5775 3304000600048 2.628 0.5531 3304000600049 2.678 0.5258 3304000600050 2.728 0.4847 3304000600051 2.778 0.4486 3304000600052 2.828 0.4259 3304000600053 2.878 0.4144 3304000600054 2.928 0.4065 3304000600055 2.978 0.3818 3304000600056 3.028 0.3270 3304000600057 3.078 0.2751 3304000600058 3.128 0.2625 3304000600059 3.178 0.2679 3304000600060 3.228 0.2825 3304000600061 3.278 0.2075 3304000600062 3.328 0.1669 3304000600063 3.378 0.1671 3304000600064 3.428 0.2066 3304000600065 3.478 0.2144 3304000600066 3.528 0.1746 3304000600067 3.578 0.1252 3304000600068 3.628 0.0890 3304000600069 3.678 0.0645 3304000600070 3.728 0.0491 3304000600071 3.778 0.0407 3304000600072 3.828 0.0377 3304000600073 3.878 0.0387 3304000600074 3.928 0.0422 3304000600075 3.978 0.0471 3304000600076 4.028 0.0527 3304000600077 4.078 0.0580 3304000600078 4.128 0.0612 3304000600079 4.178 0.0605 3304000600080 4.228 0.0542 3304000600081 4.278 0.0405 3304000600082 4.328 0.0200 3304000600083 4.378 0.0149 3304000600084 4.428 0.0397 3304000600085 4.478 0.0692 3304000600086 4.528 0.0808 3304000600087 4.578 0.0766 3304000600088 4.628 0.0639 3304000600089 4.678 0.0494 3304000600090 4.728 0.0362 3304000600091 4.778 0.0258 3304000600092 4.828 0.0196 3304000600093 4.878 0.0191 3304000600094 4.928 0.0258 3304000600095 4.978 0.0412 3304000600096 5.028 0.0679 3304000600097 5.078 0.1123 3304000600098 5.128 0.1688 3304000600099 5.178 0.2070 3304000600100 5.228 0.1934 3304000600101 5.278 0.1770 3304000600102 5.328 0.6014 3304000600103 5.378 1.9436 3304000600104 5.428 3.8096 3304000600105 5.478 5.9946 3304000600106 5.528 8.6119 3304000600107 5.578 8.4439 3304000600108 5.628 6.9564 3304000600109 5.678 4.5445 3304000600110 5.728 3.1407 3304000600111 5.778 3.7424 3304000600112 5.828 3.3107 3304000600113 5.878 6.7874 3304000600114 5.928 15.8243 3304000600115 5.978 17.5023 3304000600116 6.028 15.6199 3304000600117 6.078 12.4188 3304000600118 6.128 8.8564 3304000600119 6.178 5.2767 3304000600120 6.228 1.5354 3304000600121 6.278 0.0837 3304000600122 6.328 0.0700 3304000600123 6.378 0.0659 3304000600124 6.428 0.0281 3304000600125 ENDDATA 112 0 3304000600126 ENDSUBENT 125 0 3304000699999 SUBENT 33040007 20120617 31563304000700001 BIB 4 4 3304000700002 REACTION (3-LI-7(P,X)0-NN-1,,DA/DE,,MSC,CALC) 3304000700003 ANALYSIS Calculated using the results of C.H.Poppe at al. 3304000700004 REL-REF (R,D0038001,C.H.Poppe+,J,PR/C,14,438,1976) 3304000700005 STATUS (TABLE) Data received from P.M.Prajapati 3304000700006 ENDBIB 4 0 3304000700007 COMMON 1 3 3304000700008 EN 3304000700009 MEV 3304000700010 18. 3304000700011 ENDCOMMON 3 0 3304000700012 DATA 2 160 3304000700013 E DATA 3304000700014 MEV MB/SR/MEV 3304000700015 2.92350 1.86770 3304000700016 3.01350 1.92090 3304000700017 3.10350 1.96660 3304000700018 3.19350 2.00520 3304000700019 3.28350 2.03710 3304000700020 3.37350 2.06270 3304000700021 3.46350 2.08250 3304000700022 3.55350 2.09690 3304000700023 3.64350 2.10610 3304000700024 3.73350 2.11080 3304000700025 3.82350 2.11120 3304000700026 3.91350 2.10780 3304000700027 4.00350 2.10110 3304000700028 4.09350 2.09150 3304000700029 4.18350 2.07950 3304000700030 4.27350 2.06570 3304000700031 4.36350 2.05050 3304000700032 4.45350 2.03430 3304000700033 4.54350 2.01720 3304000700034 4.63350 1.99860 3304000700035 4.72350 1.97830 3304000700036 4.81350 1.95610 3304000700037 4.90350 1.93220 3304000700038 4.99350 1.90720 3304000700039 5.08350 1.88140 3304000700040 5.17350 1.85520 3304000700041 5.26350 1.82900 3304000700042 5.35350 1.80330 3304000700043 5.44350 1.77840 3304000700044 5.53350 1.75480 3304000700045 5.62350 1.73290 3304000700046 5.71350 1.71300 3304000700047 5.80350 1.69560 3304000700048 5.89350 1.68090 3304000700049 5.98350 1.66850 3304000700050 6.07350 1.65760 3304000700051 6.16350 1.64760 3304000700052 6.25350 1.63790 3304000700053 6.34350 1.62790 3304000700054 6.43350 1.61690 3304000700055 6.52350 1.60440 3304000700056 6.61350 1.58960 3304000700057 6.70350 1.57200 3304000700058 6.79350 1.55140 3304000700059 6.88350 1.52740 3304000700060 6.97350 1.49970 3304000700061 7.06350 1.46790 3304000700062 7.15350 1.43170 3304000700063 7.24350 1.39090 3304000700064 7.33350 1.34830 3304000700065 7.42350 1.31010 3304000700066 7.51350 1.28300 3304000700067 7.60350 1.27180 3304000700068 7.69350 1.27520 3304000700069 7.78350 1.29030 3304000700070 7.87350 1.31410 3304000700071 7.96350 1.34360 3304000700072 8.05350 1.37590 3304000700073 8.14350 1.40780 3304000700074 8.23350 1.43640 3304000700075 8.32350 1.45860 3304000700076 8.41350 1.47280 3304000700077 8.50350 1.47950 3304000700078 8.59350 1.47960 3304000700079 8.68350 1.47390 3304000700080 8.77350 1.46320 3304000700081 8.86350 1.44820 3304000700082 8.95350 1.42910 3304000700083 9.04350 1.40460 3304000700084 9.13350 1.37350 3304000700085 9.22350 1.33440 3304000700086 9.31350 1.28780 3304000700087 9.40350 1.23500 3304000700088 9.49350 1.17700 3304000700089 9.58350 1.11510 3304000700090 9.67350 1.05030 3304000700091 9.76350 0.98440 3304000700092 9.85350 0.92420 3304000700093 9.94350 0.87970 3304000700094 10.03350 0.85730 3304000700095 10.12350 0.85350 3304000700096 10.21350 0.86270 3304000700097 10.30350 0.88660 3304000700098 10.39350 0.93090 3304000700099 10.48350 1.00520 3304000700100 10.57350 1.29470 3304000700101 10.66350 1.47950 3304000700102 10.75350 1.61480 3304000700103 10.84350 1.69350 3304000700104 10.93350 1.72360 3304000700105 11.02350 1.71790 3304000700106 11.11350 1.68900 3304000700107 11.20350 1.64630 3304000700108 11.29350 1.59210 3304000700109 11.47350 1.52800 3304000700110 11.56350 1.45510 3304000700111 11.65350 1.37510 3304000700112 11.74350 1.28930 3304000700113 11.83350 1.19910 3304000700114 11.92350 1.10590 3304000700115 12.01350 1.01120 3304000700116 12.10350 0.91550 3304000700117 12.19350 0.81910 3304000700118 12.28350 0.72190 3304000700119 12.37350 0.62410 3304000700120 12.46350 0.52560 3304000700121 12.55350 0.42680 3304000700122 12.64350 0.33120 3304000700123 12.73350 0.24620 3304000700124 12.82350 0.17950 3304000700125 12.91350 0.13850 3304000700126 13.00350 0.09553 3304000700127 13.09350 0.12047 3304000700128 13.18350 0.16264 3304000700129 13.27350 0.19063 3304000700130 13.36350 0.20140 3304000700131 13.45350 0.21026 3304000700132 13.54350 0.23228 3304000700133 13.63350 0.28238 3304000700134 13.72350 0.35341 3304000700135 13.81350 0.40910 3304000700136 13.90350 0.45163 3304000700137 13.99350 0.51946 3304000700138 14.08350 0.66145 3304000700139 14.17350 0.86967 3304000700140 14.26350 1.12063 3304000700141 14.35350 1.39123 3304000700142 14.44350 1.65798 3304000700143 14.53350 1.89760 3304000700144 14.62350 2.09274 3304000700145 14.71350 2.25384 3304000700146 14.80350 2.39969 3304000700147 14.89350 2.54887 3304000700148 14.98350 2.72001 3304000700149 15.07350 2.92758 3304000700150 15.16350 3.14867 3304000700151 15.25350 3.34533 3304000700152 15.34350 3.49596 3304000700153 15.43350 3.58379 3304000700154 15.52350 3.62298 3304000700155 15.61350 3.66681 3304000700156 15.70350 3.77114 3304000700157 15.79350 3.99179 3304000700158 15.88350 4.38402 3304000700159 15.97350 4.90566 3304000700160 16.06350 5.30029 3304000700161 16.15350 5.28313 3304000700162 16.24350 4.56934 3304000700163 16.33350 3.23613 3304000700164 16.42350 2.73579 3304000700165 16.51350 2.34014 3304000700166 16.60350 1.67812 3304000700167 16.69350 1.44823 3304000700168 16.78350 1.48509 3304000700169 16.87350 1.64140 3304000700170 16.96350 1.82396 3304000700171 17.05350 1.94021 3304000700172 17.14350 1.89760 3304000700173 17.23350 1.60381 3304000700174 17.32350 0.96629 3304000700175 ENDDATA 162 0 3304000700176 ENDSUBENT 175 0 3304000799999 ENDENTRY 7 0 3304099999999