ENTRY 33044 20180524 31853304400000001 SUBENT 33044001 20180524 31853304400100001 BIB 15 49 3304400100002 TITLE Measurement of 232Th(n,g) and 232Th(n,2n) 3304400100003 cross-sections at neutron energies of 13.5, 15.5 and 3304400100004 17.28 MeV using neutron activation techniques 3304400100005 AUTHOR (S.Mukerji, H.Naik, S.V.Suryanarayana, S.Chachara, 3304400100006 B.S.Shivashankar, V.Mulik, R.Crasta, S.Samanta, 3304400100007 B.K.Nayak, A.Saxena, S.C.Sharma, P.V.Bhagwat, 3304400100008 K.K.Rasheed, R.N.Jindal, S.Ganesan, A.K.Mohanty, 3304400100009 A.Goswami, P.D.Krishnani) 3304400100010 INSTITUTE (3INDTRM,3INDMNP,3INDPOO,3INDMNG) 3304400100011 REFERENCE (J,PRM,79,249,2012) 3304400100012 FACILITY (VDGT,3INDTRM) 14UD BARC-TIFR Pelletron 3304400100013 INC-SOURCE (P-LI7) Natural Li (3.7 mg/cm2) sandwiched between two 3304400100014 Ta foils of different thicknesses (30 keV thick one 3304400100015 faced the proton beam and 1.0 mm thick one behind the 3304400100016 Li foil) 3304400100017 SAMPLE Th metal foil of 1 cm2 length and 0.025 mm thickness 3304400100018 behind the Ta-Li-Ta stack. 3304400100019 The foil was wrapped with 0.025 mm thick superpure 3304400100020 aluminum foil 3304400100021 METHOD (ACTIV,GSPEC) Irradiated for 5-7 hrs and cooled for 3304400100022 6-24 hrs. 3304400100023 DETECTOR (HPGE) Coaxial p-type HPGe detector (66.2 mm diam., 3304400100024 66.7 mm height) with a relative efficiency of 50% and 3304400100025 the resolution of 2 keV at 1332.5 keV of 60Co. 3304400100026 MONITOR (90-TH-232(N,F)53-I-131,(CUM),FY) 3304400100027 (90-TH-232(N,F)52-TE-132,(CUM),FY) 3304400100028 (90-TH-232(N,F)40-ZR-97,(CUM),FY) 3304400100029 MONIT-REF (12257001,R.L.Henkel,R,LA-2122,1957) 3304400100030 232Th(n,f) cross section given 3304400100031 (22797001,C.Paradela+,C,2006VANCOU,,(B076),2006) 3304400100032 232Th(n,f) cross section given 3304400100033 (10920001,L.E.Glendenin+,J,PR/C,22,152,1980) 3304400100034 232Th(n,f) fission yield given 3304400100035 (,E.A.C.Crouch,J,AND,19,417,1977) 3304400100036 232Th(n,f) fission yield given 3304400100037 REL-REF (R,D0038001,C.H.Poppe+,J,PR/C,14,438,1976) 3304400100038 7Li(p,n) neutron distribution given 3304400100039 (R,,S.G.Mashnik+,R,LA-UR-00-5524,2000) 3304400100040 7Li(p,n) neutron distribution given 3304400100041 ERR-ANALYS (ERR-T) Quadratic sum of 3304400100042 (ERR-S,5.,10.) Counting statistics (5-10%) 3304400100043 (ERR-1) neutron flux estimation (~2%) 3304400100044 (ERR-2) irradiation time (~0.5%) 3304400100045 (ERR-3) detection efficiency calibration (~3%) 3304400100046 (ERR-4) half-life and gamma-ray abundances (~2%) 3304400100047 STATUS (TABLE) Table 2 of Pramana 79(2012)249 3304400100048 (APRVD) Entry approved by author 3304400100049 HISTORY (20130301C) A.Chakraborty & Sadhana Mukerji 3304400100050 (20180524U) On. MONIT-REF corrected. 3304400100051 ENDBIB 49 0 3304400100052 COMMON 4 3 3304400100053 ERR-1 ERR-2 ERR-3 ERR-4 3304400100054 PER-CENT PER-CENT PER-CENT PER-CENT 3304400100055 2. 0.5 3. 2. 3304400100056 ENDCOMMON 3 0 3304400100057 ENDSUBENT 56 0 3304400199999 SUBENT 33044002 20130301 31593304400200001 BIB 6 17 3304400200002 REACTION (90-TH-232(N,G)90-TH-233,,SIG) 3304400200003 DECAY-DATA (90-TH-233,21.83MIN,DG,86.5,0.027) 3304400200004 (91-PA-233,26.975D,DG,311.9,0.384) 3304400200005 RAD-DET (91-PA-233,DG) 3304400200006 INC-SPECT Neutron flux is 3304400200007 (9.65 +- 0.76) x 10**6 n/cm2/s at 13.50 MeV 3304400200008 (3.09 +- 0.25) x 10**7 n/cm2/s at 15.50 MeV 3304400200009 (8.59 +- 0.67) x 10**7 n/cm2/s at 17.28 MeV 3304400200010 CORRECTION The contribution from the tail region has been 3304400200011 estimated using the ENDF/B-VII.0 and JENDL-4.0 by 3304400200012 folding the cross-sections with neutron flux 3304400200013 distributions in Poppe et al. (1976) and S.Mashnik et 3304400200014 al. (2008). The actual value due to the neutrons from 3304400200015 the main peak of the n0 and n1 groups of the neutron 3304400200016 spectrum is obtained after subtracting the average 3304400200017 cross-section due to neutrons from the tail region. 3304400200018 MISC-COL (MISC) Cross section not corrected for tail neutrons 3304400200019 ENDBIB 17 0 3304400200020 NOCOMMON 0 0 3304400200021 DATA 6 3 3304400200022 EN EN-ERR DATA ERR-T MISC MISC-ERR 3304400200023 MEV MEV MB MB MB MB 3304400200024 13.50 0.35 1.052 0.166 2.49 0.15 3304400200025 15.50 0.5 0.701 0.171 2.34 0.15 3304400200026 17.28 0.35 0.503 0.141 1.569 0.141 3304400200027 ENDDATA 5 0 3304400200028 ENDSUBENT 27 0 3304400299999 SUBENT 33044003 20130301 31593304400300001 BIB 3 8 3304400300002 REACTION (90-TH-232(N,2N)90-TH-231,,SIG) 3304400300003 INC-SPECT Neutron flux (7.02 +- 0.55) x 10**7 n/cm2/s 3304400300004 Value was obtained based on the ratio of the 3304400300005 neutron flux of the neutron spectrum for (n,2n) 3304400300006 reaction in C.H.Poppe et al. (1976) and 3304400300007 S.G.Mashnik et al. (2000) above its threshold to the 3304400300008 total flux. 3304400300009 DECAY-DATA (90-TH-231,25.52HR,DG,84.2,0.066) 3304400300010 ENDBIB 8 0 3304400300011 NOCOMMON 0 0 3304400300012 DATA 4 1 3304400300013 EN EN-ERR DATA ERR-T 3304400300014 MEV MEV MB MB 3304400300015 17.28 0.35 656. 99. 3304400300016 ENDDATA 3 0 3304400300017 ENDSUBENT 16 0 3304400399999 ENDENTRY 3 0 3304499999999