ENTRY 41420 20130529 41614142000000001 SUBENT 41420001 20130529 41614142000100001 BIB 13 36 4142000100002 TITLE Thermal neutron capture cross section of 232Pa 4142000100003 AUTHOR (M.Andreev, S.Abramovich, E.Fomushkin, V.Kvasov, 4142000100004 A.Portnov, A.Redkin, H.Yasuda) 4142000100005 INSTITUTE (4RUSMIF) Kvasov, Portnov, Redkin 4142000100006 (4RUSEPA) Andreev, Abramovich, Fomushkin 4142000100007 (2JPNJAE) Yasuda 4142000100008 REFERENCE (J,NSTS,2,(1),280,200208) Main reference, data given 4142000100009 Conf.Proc. ND2011 in Tsukuba . 4142000100010 (C,97TRIEST,2,1356,199705) Experimental and analysis 4142000100011 details 4142000100012 REL-REF (R,,F.F.Fomushkin+,C,97TRIEST,2,1353,199705) 4142000100013 FACILITY (REAC,4RUSMIF) Research thermal reactor RTR of 4RUSMIF 4142000100014 INC-SOURCE (REAC) 4142000100015 INC-SPECT Density of the thermal neutron flux at irradiation 4142000100016 position 0.29E+18 n/s/m**2. Cd ratio by Au-198 isotope 4142000100017 was 4.8 . 4142000100018 DETECTOR (HPGE,GELI) 4142000100019 METHOD (ACTIV) Activation during 20 hr in channel VEC-4 4142000100020 filled with water. One sample was irradiated inside Cd 4142000100021 cover. Cooling time 5 days, measuring time 35 days. 4142000100022 (GSPEC) Gamma-Spectrum analysis was performed at the 4142000100023 measuring complex at 4RUSEPA consisting of 4142000100024 Ge(Li) detector and SBS-40 analyser produced 4142000100025 by GREEN STAR firm 4142000100026 (SITA) Single-target irradiation 4142000100027 DECAY-DATA (91-PA-231,3.38E+4YR) 4142000100028 COMMENT NSTS,2,(1),280,2002 was performed within the frames of 4142000100029 ISTC Project #1145. 4142000100030 HISTORY (20030103C) + + Compiled at the center - CJD + + 4142000100031 (20030104U) Last checking has been done. 4142000100032 (20130529A) Ref. C,2001TSUKUB,,(73),200110 was deleted 4142000100033 according to the memo CP-D/791 ( N.Otsuka,S.Dunaeva) . 4142000100034 Upper -> lower case correction. 4142000100035 MXW was deleted in REACTION, EN-MEAN -> EN, ERR-T -> 4142000100036 DATA-ERR in Subent 2. 4142000100037 Subent 003 was added. 4142000100038 ENDBIB 36 0 4142000100039 NOCOMMON 0 0 4142000100040 ENDSUBENT 39 0 4142000199999 SUBENT 41420002 20130529 41614142000200001 BIB 4 7 4142000200002 REACTION (91-PA-232(N,G)91-PA-233,,SIG) 4142000200003 ANALYSIS .Cross-section for 0.0253 eV energy was obtained from 4142000200004 the measured one using 1/V energy dependence law 4142000200005 extrapolation. 4142000200006 ERR-ANALYS (DATA-ERR) Not specified by authors. 4142000200007 STATUS (TABLE) Text, page 282 of J,NSTS,2,(1),280,2002. 4142000200008 (DEP,41420003) Directly measured data. 4142000200009 ENDBIB 7 0 4142000200010 NOCOMMON 0 0 4142000200011 DATA 3 1 4142000200012 EN DATA DATA-ERR 4142000200013 EV B B 4142000200014 0.0253 655. 69. 4142000200015 ENDDATA 3 0 4142000200016 ENDSUBENT 15 0 4142000299999 SUBENT 41420003 20130529 41614142000300001 BIB 8 34 4142000300002 REACTION (91-PA-232(N,G)91-PA-233,,SIG,,MXW) 4142000300003 DECAY-DATA (91-PA-232,31.44HR,B-,,,DG) 4142000300004 (91-PA-233,27.D,B-,,,DG,312.2,0.386) 4142000300005 INC-SPECT .Average thermal neutron energy is 0.0273 eV . 4142000300006 Calculated spectrum is on Fig.2 of NSTS,2,(1),280,2002.4142000300007 ANALYSIS Weighted average value of two methods: 4142000300008 - by amount of Pa233 atoms built up during irradiation:4142000300009 518+-126 barn ; 4142000300010 - by ratio of built-up quantities of Pa233 and Pa232 4142000300011 (o.639=-0.068)*10**-3 : 653+-91 barn. 4142000300012 ASSUMED (ASSUM1,91-PA-231(N,F),,SIG,,MXW) 4142000300013 (ASSUM2,91-PA-232(N,F),,SIG,,MXW) 4142000300014 (ASSUM3,91-PA-233(N,G)91-PA-234,,SIG,,MXW) 4142000300015 (ASSUM4,91-PA-233(N,F),,SIG,,MXW) 4142000300016 (ASSUM5,91-PA-231(N,G)91-PA-232,,SIG,,MXW) 4142000300017 Westcott factors for neutron radiation c-s 1.0165 for 4142000300018 Pa231 and 0.9625 for Pa-232. 4142000300019 Decay constants 6.124E-6 /s for Pa232, 2.971E-7 /s for 4142000300020 Pa233. 4142000300021 SAMPLE .Disk of protactinium-231 placed in a titanium foil 4142000300022 5.E-5 meter thick. Two samples were prepared, one 4142000300023 containing N1=(0,478+-0.004)E-4 gram, another - 4142000300024 N2=(0.563+-0.003)E-4 gram of 231Pa. 4142000300025 .Pa-232 sample was obtained by building up during 4142000300026 Pa-231 sample irradiation in the reactor and deter- 4142000300027 mined using seven gamma-lines accompanying Pa-232 4142000300028 beta decay. Number of Pa-232 atoms is N1(PA-232)= 4142000300029 (3.360+-0.085)E+13. 4142000300030 .Pa-233 build-up quantity was defined by a 312.2-keV 4142000300031 gamma-line accompanying Pa-233 beta decay. Numbers of 4142000300032 Pa-233 atoms are - N1(PA-233)=(2.39+-0.22)E+10, 4142000300033 N2(PA-233)=(0.117+-0.032)E+10 4142000300034 ERR-ANALYS (DATA-ERR) Not specified by authors. 4142000300035 STATUS (TABLE) Text, page 282 of J,NSTS,2,(1),280,2002. 4142000300036 ENDBIB 34 0 4142000300037 COMMON 5 3 4142000300038 ASSUM1 ASSUM2 ASSUM3 ASSUM4 ASSUM5 4142000300039 B B B B B 4142000300040 0.014 955. 39. 0. 204. 4142000300041 ENDCOMMON 3 0 4142000300042 DATA 3 1 4142000300043 EN DATA DATA-ERR 4142000300044 EV B B 4142000300045 0.0273 607. 64. 4142000300046 ENDDATA 3 0 4142000300047 ENDSUBENT 46 0 4142000399999 ENDENTRY 3 0 4142099999999