ENTRY 14328 20120816 13861432800000001 SUBENT 14328001 20120816 13861432800100001 BIB 15 50 1432800100002 TITLE Evaluation of Neutron Inelastic Scattering for 1432800100003 Radioisotope Production 1432800100004 AUTHOR (S.Mirzadeh,F.F.Knapp Jr,C.W.Alexander,L.F.Mausner) 1432800100005 INSTITUTE (1USAORL,1USABNL) 1432800100006 FACILITY (REAC,1USAORL) 1432800100007 REFERENCE (J,ARI,48,(4),441,1997) 1432800100008 #doi:10.1016/S0969-8043(96)00284-9 1432800100009 INC-SOURCE (REAC) ORNL High Flux Isotope Reactor. 1432800100010 INC-SPECT Reactor neutrons 1432800100011 DETECTOR (HPGE) 50 cm3, 1-cm-thick EG&G Ortec solid state 1432800100012 detector. 1432800100013 PART-DET (G) 1432800100014 SAMPLE The targets were sealed under 1432800100015 slight negative pressure of He in quartz ampules (6.7 1432800100016 x 51 mm). The sealed quartz ampules were then placed 1432800100017 in the welded Al rabbits (6.7 x 51 mm) for 1432800100018 irradiation. 1432800100019 METHOD (ACTIV,GSPEC,RCHEM) After the irradiation, the quartz 1432800100020 samples were soaked in HNO3 to remove surface 1432800100021 contamination. After the appropriate cooling time, 1432800100022 the activities were measured at a 30 cm distance from 1432800100023 a well-calibrated HPGe detector. 1432800100024 ANALYSIS (PGS) All activities were followed for several half- 1432800100025 lives and the activities at the end of bombardment 1432800100026 were extrapolated by the CLSQ code. When the multiple 1432800100027 gamma-rays were used for assay, their intensities 1432800100028 were used as weighing factors in calculations of the 1432800100029 average activity values. The relevant nuclear data 1432800100030 were taken from Lederer et al., Reus and Westmeier, 1432800100031 and Mughabghab. The fission-averaged cross sections 1432800100032 for the individual reactions, sigma, leading to 1432800100033 117mSn, 119mSn and 195mPt were calculated by solving 1432800100034 sets of three simultaneous equations for each 1432800100035 radioisotope. 1432800100036 ERR-ANALYS (ERR-T) It includes uncertainty due to counting 1432800100037 statistics and detector efficiency. The uncertainty 1432800100038 for thermal cross sections and resonance integrals 1432800100039 includes 1432800100040 (ERR-1) 5% error in thermal-to-epithermal ratio. 1432800100041 ADD-RES This article contains data on fission-averaged 1432800100042 cross sections for Oak Ridge High Flux Isotope 1432800100043 Reactor (HFIR) spectrum and 116Sn(n,gamma), 1432800100044 117Sn(n,n'), 118Sn(n,2n), 118Sn(n,gamma), 1432800100045 119Sn(n,n'), 120Sn(n,2n), 194Pt(n,gamma), 195Pt(n,n') 1432800100046 and 196Pt(n,2n) reactions. Unfortunately, these data 1432800100047 are given for integral cross sections and Oak Ridge 1432800100048 reactor neutron spectrum. This reactor neutron 1432800100049 spectrum is not well defined, please see Table 2. 1432800100050 Consequently, these data were not compiled. 1432800100051 HISTORY (20120816C) BP 1432800100052 ENDBIB 50 0 1432800100053 COMMON 1 3 1432800100054 ERR-1 1432800100055 PER-CENT 1432800100056 5. 1432800100057 ENDCOMMON 3 0 1432800100058 ENDSUBENT 57 0 1432800199999 SUBENT 14328002 20120816 13861432800200001 BIB 4 4 1432800200002 REACTION (50-SN-116(N,G)50-SN-117-M,,SIG,,MXW) 1432800200003 SAMPLE (50-SN-116,ENR=0.9650) 1432800200004 STATUS (TABLE) Table 3, page 443. 1432800200005 DECAY-DATA (50-SN-117-M,14.0D) 1432800200006 ENDBIB 4 0 1432800200007 NOCOMMON 0 0 1432800200008 DATA 3 1 1432800200009 EN-DUMMY DATA ERR-T 1432800200010 EV MB MB 1432800200011 0.0253 5.8 1.2 1432800200012 ENDDATA 3 0 1432800200013 ENDSUBENT 12 0 1432800299999 SUBENT 14328003 20120816 13861432800300001 BIB 4 4 1432800300002 REACTION (50-SN-116(N,G)50-SN-117-M,,RI) 1432800300003 SAMPLE (50-SN-116,ENR=0.9650) 1432800300004 STATUS (TABLE) Table 3, page 443. 1432800300005 DECAY-DATA (50-SN-117-M,14.0D) 1432800300006 ENDBIB 4 0 1432800300007 NOCOMMON 0 0 1432800300008 DATA 3 1 1432800300009 EN-MIN DATA ERR-T 1432800300010 EV MB MB 1432800300011 0.5 350. 53. 1432800300012 ENDDATA 3 0 1432800300013 ENDSUBENT 12 0 1432800399999 SUBENT 14328004 20120816 13861432800400001 BIB 4 4 1432800400002 REACTION (50-SN-118(N,G)50-SN-119-M,,SIG,,MXW) 1432800400003 SAMPLE (50-SN-118,ENR=0.9707) 1432800400004 STATUS (TABLE) Table 3, page 443. 1432800400005 DECAY-DATA (50-SN-119-M,293.D) 1432800400006 ENDBIB 4 0 1432800400007 NOCOMMON 0 0 1432800400008 DATA 3 1 1432800400009 EN-DUMMY DATA ERR-T 1432800400010 EV MB MB 1432800400011 0.0253 7.4 2.0 1432800400012 ENDDATA 3 0 1432800400013 ENDSUBENT 12 0 1432800499999 SUBENT 14328005 20120816 13861432800500001 BIB 4 4 1432800500002 REACTION (50-SN-118(N,G)50-SN-119-M,,RI) 1432800500003 SAMPLE (50-SN-118,ENR=0.9707) 1432800500004 STATUS (TABLE) Table 3, page 443. 1432800500005 DECAY-DATA (50-SN-119-M,293.D) 1432800500006 ENDBIB 4 0 1432800500007 NOCOMMON 0 0 1432800500008 DATA 3 1 1432800500009 EN-MIN DATA ERR-T 1432800500010 EV MB MB 1432800500011 0.5 144. 22. 1432800500012 ENDDATA 3 0 1432800500013 ENDSUBENT 12 0 1432800599999 SUBENT 14328006 20120816 13861432800600001 BIB 4 4 1432800600002 REACTION (78-PT-194(N,G)78-PT-195-M,,SIG,,MXW) 1432800600003 SAMPLE (78-PT-194,ENR=0.9741) 1432800600004 STATUS (TABLE) Table 3, page 443. 1432800600005 DECAY-DATA (78-PT-195-M,4.02D) 1432800600006 ENDBIB 4 0 1432800600007 NOCOMMON 0 0 1432800600008 DATA 3 1 1432800600009 EN-DUMMY DATA ERR-T 1432800600010 EV MB MB 1432800600011 0.0253 42. 8. 1432800600012 ENDDATA 3 0 1432800600013 ENDSUBENT 12 0 1432800699999 SUBENT 14328007 20120816 13861432800700001 BIB 4 4 1432800700002 REACTION (78-PT-194(N,G)78-PT-195-M,,RI) 1432800700003 SAMPLE (78-PT-194,ENR=0.9741) 1432800700004 STATUS (TABLE) Table 3, page 443. 1432800700005 DECAY-DATA (78-PT-195-M,4.02D) 1432800700006 ENDBIB 4 0 1432800700007 NOCOMMON 0 0 1432800700008 DATA 3 1 1432800700009 EN-MIN DATA ERR-T 1432800700010 EV MB MB 1432800700011 0.5 526. 79. 1432800700012 ENDDATA 3 0 1432800700013 ENDSUBENT 12 0 1432800799999 ENDENTRY 7 0 1432899999999