ENTRY 33042 20180524 31853304200000001 SUBENT 33042001 20180524 31853304200100001 BIB 15 43 3304200100002 TITLE Measurement of the 232Th(n,g)233Th and 3304200100003 232Th(n,2n)231Th reaction cross-sections at neutron 3304200100004 energies of 8.04 +/- 0.30 and 11.90 +/- 0.35 MeV 3304200100005 AUTHOR (R.Crasta, H.Naik, S.V.Suryanarayana, B.S.Shivashankar,3304200100006 V.K.Mulik, P.M.Prajapati, G.Sanjeev, S.C.Sharma, 3304200100007 P.V.Bhagwat, A.K.Mohanty, S.Ganesan, A.Goswami) 3304200100008 INSTITUTE (3INDMNG,3INDTRM,3INDMNP,3INDPOO,3INDBDA) 3304200100009 REFERENCE (J,ANE,47,160,2012) 3304200100010 FACILITY (VDGT,3INDTRM) 14 UD BARC-TIFR Pelletron 3304200100011 INC-SOURCE (P-LI7) Natural Li (3.7 mg/cm2) sandwiched between two 3304200100012 Ta foils of different thicknesses (30 keV thick one 3304200100013 faced the proton beam and 0.025 mm thick one behind 3304200100014 the Li foil) 3304200100015 SAMPLE Th metal foil (143.8 mg/cm2 thick) wrapped with super 3304200100016 pure Al foil (0.025 mm thick) 3304200100017 DETECTOR (HPGE) 80 cm3 HPGe detector 3304200100018 METHOD (ACTIV,GSPEC) The samples were irradiated for 5-7 hrs, 3304200100019 and cooled for sufficient cooling time after 3304200100020 irradiation. 3304200100021 MONITOR (90-TH-232(N,F)53-I-135,(CUM),FY) 3304200100022 (90-TH-232(N,F)40-ZR-97,(CUM),FY) 3304200100023 MONIT-REF (12257001,R.L.Henkel,R,LA-2122,1957) 3304200100024 232Th(n,f) cross section 3304200100025 (22797001,C.Paradela+,C,2006VANCOU,,(B076),2006) 3304200100026 232Th(n,f) cross section 3304200100027 (,E.A.C.Crouch,J,AND,19,417,1977) 3304200100028 232Th(n,f) fission yield 3304200100029 (10920001,L.E.Glendenin+,J,PR/C,22,152,1980) 3304200100030 232Th(n,f) fission yield 3304200100031 REL-REF (R,D0038001,C.H.Poppe+,J,PR/C,14,438,1976) 3304200100032 7Li(p,n) neutron distribution given 3304200100033 (R,,S.G.Mashnik+,R,LA-UR-00-5524,2000) 3304200100034 7Li(p,n) neutron distribution given 3304200100035 ERR-ANALYS (ERR-T) Quadratic sum of 3304200100036 (ERR-S,5.,10.) Counting statistics (5-10%) 3304200100037 (ERR-1) neutron flux estimation (~2%) 3304200100038 (ERR-2) irradiation time (~0.5%) 3304200100039 (ERR-3) detection efficiency calibration (~3%) 3304200100040 (ERR-4) half-life and gamma-ray abundances (~2%) 3304200100041 STATUS (TABLE) Table 2 of Ann.Nucl.Energy 47(2012)160 3304200100042 (APRVD) Entry approved by Dr. H.Naik 3304200100043 HISTORY (20130219C) S Subramanian 3304200100044 (20180524U) On. MONIT-REF corrected. 3304200100045 ENDBIB 43 0 3304200100046 COMMON 4 3 3304200100047 ERR-1 ERR-2 ERR-3 ERR-4 3304200100048 PER-CENT PER-CENT PER-CENT PER-CENT 3304200100049 2. 0.5 3. 2. 3304200100050 ENDCOMMON 3 0 3304200100051 ENDSUBENT 50 0 3304200199999 SUBENT 33042002 20130219 31593304200200001 BIB 6 18 3304200200002 REACTION (90-TH-232(N,G)90-TH-233,,SIG) 3304200200003 DECAY-DATA (90-TH-233,21.83MIN,DG,86.5,0.027) 3304200200004 (91-PA-233,26.975D,DG,311.9,0.384) 3304200200005 RAD-DET (91-PA-233,DG) 3304200200006 INC-SPECT The neutron flux calculated for 8.04 +- 0.30 MeV and 3304200200007 11.90 +- 0.35 MeV neutron energies are obtained to be 3304200200008 (3.56 +- 0.03) x 10**6 and (1.30 +- 0.02) x 10**7 3304200200009 n/cm2/s corresponding to the proton energy of 10 3304200200010 and 14 MeV,respectively. 3304200200011 CORRECTION The contribution from the tail region has been 3304200200012 estimated using the ENDF/B-VII.0 and JENDL-4.0 by 3304200200013 folding the cross-sections with neutron flux 3304200200014 distributions in Poppe et al. (1976) and S.Mashnik et 3304200200015 al. (2008). The actual value due to the neutrons from 3304200200016 the main peak of the n0 and n1 groups of the neutron 3304200200017 spectrum is obtained after subtracting the average 3304200200018 cross-section due to neutrons from the tail region. 3304200200019 MISC-COL (MISC) Cross section before tail neutron correction 3304200200020 ENDBIB 18 0 3304200200021 NOCOMMON 0 0 3304200200022 DATA 6 2 3304200200023 EN EN-ERR DATA ERR-T MISC MISC-ERR 3304200200024 MEV MEV MB MB MB MB 3304200200025 8.04 0.30 0.77 0.08 4.52 0.083304200200026 11.90 0.35 1.12 0.02 2.24 0.023304200200027 ENDDATA 4 0 3304200200028 ENDSUBENT 27 0 3304200299999 SUBENT 33042003 20130220 31593304200300001 BIB 3 11 3304200300002 REACTION (90-TH-232(N,2N)90-TH-231,,SIG) 3304200300003 DECAY-DATA (90-TH-231,25.52HR,DG,84.2,0.066) 3304200300004 INC-SPECT The neutron flux for the 232Th(n,2n) reaction at the 3304200300005 average neutron energies of 8.04 +- 0.30 MeV and 3304200300006 11.90 +- 0.35 MeV were obtained as 3304200300007 (2.34 +- 0.02) x 10**6 and 3304200300008 (9.06 +- 0.02) x 10**6 n/cm2/s, respectively. 3304200300009 These values were obtained based on the ratio of 3304200300010 neutron flux of the neutron spectrum of Refs. Poppe et 3304200300011 al.(1976) and Mashnik et al.(2008) for (n,2n) reaction 3304200300012 above its threshold to total flux. 3304200300013 ENDBIB 11 0 3304200300014 NOCOMMON 0 0 3304200300015 DATA 4 2 3304200300016 EN EN-ERR DATA ERR-T 3304200300017 MEV MEV MB MB 3304200300018 8.04 0.30 1566.29 62.11 3304200300019 11.90 0.35 2097.93 25.13 3304200300020 ENDDATA 4 0 3304200300021 ENDSUBENT 20 0 3304200399999 ENDENTRY 3 0 3304299999999