ENTRY 41560 20200120 41864156000000001 SUBENT 41560001 20200120 41864156000100001 BIB 14 38 4156000100002 INSTITUTE (4RUSFEI) 4156000100003 REFERENCE (R,ICD-6,42,1969) Main ref. 4156000100004 (R,LA-TR-71-74,1971) Engl.transl. of ICD-6,42,1969. 4156000100005 In INDC(CCP)-0012,1971 - title and authors list in 4156000100006 English. 4156000100007 AUTHOR (A.G.Dovbenko,V.I.Ivanov,V.E.Kolesov,V.A.Tolstikov) 4156000100008 TITLE Am-241 radiative neutron capture. 4156000100009 REL-REF (I,,A.I.Leypunskii+,J,AE,11,(6),498,1961) 4156000100010 Details of BR-5 reactor; measured data to estimate 4156000100011 neutron beam. 4156000100012 (M,,V.I.Ivanov+,J,AE,16,(6),497,1964) 4156000100013 Details of correction of neutron beam. 4156000100014 FACILITY (REAC) BR-5 reactor. 4156000100015 METHOD (ACTIV) 145 days activation. 1 year cooling. 4156000100016 Activation as in reactor core as in thermal column. 4156000100017 (CHSEP) Am-241 and Cm-242 were radio-chemically 4156000100018 separated. 4156000100019 (ASPEC) Alpha-spectrometry from May 1962 to March 1969.4156000100020 SAMPLE Ionization alpha-spectrometer was used to measure 4156000100021 alpha-activities of samples. 4156000100022 DETECTOR (FISCH) Pu-239 fission chamber to measure absolute 4156000100023 neutron beam in reactor core. 4156000100024 EXP-YEAR (1960) Activation started 01.07.1960. 4156000100025 DECAY-DATA (95-AM-242-G,16.HR,B-,,0.84) 4156000100026 (95-AM-242-M,152.YR) 4156000100027 RAD-DET (96-CM-242,A) 4156000100028 ANALYSIS Least squares method was used to define ratio 4156000100029 of activities of produced Cm-242 and initial Am-241. 4156000100030 HISTORY (20110405C) M.M. 4156000100031 (20120323A) Misprint in EN units was corrected in 4156000100032 Subents 004,005. 4156000100033 (20131219A) Ref.R,LA-TR-71-74,1971 was added. 4156000100034 Comments of compiler were added in Subents 004,005. 4156000100035 (20140704A) SPSDD, OUTDT were added in STATUS of 4156000100036 Subents 002, 003, respectively. 4156000100037 (20141220U) Minor free text correction in Subent 004. 4156000100038 (20200120U) "EC,,0.16" was deleted from DECAY-DATA, 4156000100039 RAD-DET was added . 4156000100040 ENDBIB 38 0 4156000100041 NOCOMMON 0 0 4156000100042 ENDSUBENT 41 0 4156000199999 SUBENT 41560002 20140704 41644156000200001 BIB 7 23 4156000200002 REACTION 1(95-AM-241(N,G)95-AM-242-G,,SIG,,SPA) 4156000200003 2(95-AM-241(N,G)95-AM-242-M,,SIG,,SPA) 4156000200004 3(95-AM-241(N,G)95-AM-242,,SIG,,SPA) 4156000200005 INC-SOURCE (REAC) Reactor BR-5 active core. 5 MW power. 4156000200006 INC-SPECT Neutron beam in the reactor active core center taking 4156000200007 into account correction -see REL-REF of V.I.Ivanov+. 4156000200008 was defined to be (9.45+-0.5)*10**14 n/sec; 4156000200009 at activation place - (6.6 +- 0.4)*10**14 n/sec. 4156000200010 Integral neutron beam for sample was 4156000200011 (8.25 +- 0.50) n/cm**2. 4156000200012 Average neutron energy in reactor core at activation 4156000200013 place - 0.3 MeV. 4156000200014 DETECTOR (FISCH) Pu-239 fission chamber to measure absolute 4156000200015 neutron beam in reactor core. 4156000200016 MONITOR ((MONIT)94-PU-239(N,F),,SIG) - for neutron flux in 4156000200017 reactor. 4156000200018 ERR-ANALYS (DATA-ERR) Not specified. 4156000200019 STATUS (TABLE) Text, pages 43-44, of R,ICD-6,42,1969. 4156000200020 (SPSDD,40308002) In 40308 data were re-normalized by 4156000200021 (SPSDD,40308003) authors for new monitor and Am-241 4156000200022 (SPSDD,40308004) half-life values. Also mistake in 4156000200023 calculation of accumulated Am-242-g was corrected in 4156000200024 40308. 4156000200025 ENDBIB 23 0 4156000200026 COMMON 3 3 4156000200027 EN-MEAN MONIT MONIT-ERR 4156000200028 MEV B B 4156000200029 0.3 1.80 0.09 4156000200030 ENDCOMMON 3 0 4156000200031 DATA 6 1 4156000200032 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 34156000200033 MB MB MB MB MB MB 4156000200034 790. 90. 150. 14. 940. 93. 4156000200035 ENDDATA 3 0 4156000200036 ENDSUBENT 35 0 4156000299999 SUBENT 41560003 20140704 41644156000300001 BIB 4 7 4156000300002 REACTION (95-AM-241(N,G)95-AM-242-M/T,,SIG/RAT,,SPA,DERIV) 4156000300003 INC-SOURCE (REAC) Reactor BR-5 active core. 5 MW power. 4156000300004 ERR-ANALYS (DATA-ERR) Not specified. 4156000300005 STATUS (TABLE) Text, page 44, of R,ICD-6,42,1969. 4156000300006 (DEP,41560002) Derived from c-s. 4156000300007 (OUTDT,40308005) See Entry 40308 (Subent 005) 4156000300008 for isomeric ratio re-normalized by authors . 4156000300009 ENDBIB 7 0 4156000300010 COMMON 1 3 4156000300011 EN-MEAN 4156000300012 MEV 4156000300013 0.3 4156000300014 ENDCOMMON 3 0 4156000300015 DATA 2 1 4156000300016 DATA DATA-ERR 4156000300017 NO-DIM NO-DIM 4156000300018 0.160 0.022 4156000300019 ENDDATA 3 0 4156000300020 ENDSUBENT 19 0 4156000399999 SUBENT 41560004 20141220 41664156000400001 BIB 6 14 4156000400002 REACTION 1(95-AM-241(N,G)95-AM-242-G,,SIG,,MXW) 4156000400003 2(95-AM-241(N,G)95-AM-242-M,,SIG,,MXW) 4156000400004 3(95-AM-241(N,G)95-AM-242,,SIG,,MXW) 4156000400005 INC-SOURCE (THCOL) Thermal column K-2. 4156000400006 INC-SPECT For thermal column the integral neutron beam was 4156000400007 defined from Pu-239, Pu-240, U-235 radiative capture 4156000400008 measurement by mass spectrometer MI-1306 to be 4156000400009 (3.40 +- 0.45)*10**18 n/cm**2. 4156000400010 COMMENT Of evaluator K.Zolotarev. There is misprint in the 4156000400011 article: 674.b -> 647.b . 4156000400012 Of compiler M.M. In R,LA-TR-71-74,1971 the value of 4156000400013 AM-241(N,G)95-AM-242,,SIG (DATA 3) is given as 647 b. 4156000400014 ERR-ANALYS (DATA-ERR) Not specified. 4156000400015 STATUS (TABLE) Text, page 44, of R,ICD-6,42,1969. 4156000400016 ENDBIB 14 0 4156000400017 COMMON 1 3 4156000400018 EN-DUMMY 4156000400019 EV 4156000400020 0.0253 4156000400021 ENDCOMMON 3 0 4156000400022 DATA 6 1 4156000400023 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 34156000400024 B B B B B B 4156000400025 573. 103. 74. 15. 647. 104. 4156000400026 ENDDATA 3 0 4156000400027 ENDSUBENT 26 0 4156000499999 SUBENT 41560005 20131219 41624156000500001 BIB 5 16 4156000500002 REACTION (95-AM-241(N,G)95-AM-242-M/T,,SIG/RAT,,MXW,DERIV) 4156000500003 INC-SOURCE (THCOL) Thermal column K-2. 4156000500004 COMMENT Of compiler M.M. 4156000500005 As mentioned in the article, the isomeric ratio was 4156000500006 obtained from measured cross-sections ( given in Subent4156000500007 004). Using thes cross-sections the isomeric ratio M/T 4156000500008 is calculated as 74./647. = 0.114374 - this is not 4156000500009 equal to values given : 4156000500010 in R,ICD-6,42,1969 - 0.118 , 4156000500011 in R,LA-TR-71-74,1971 ( Engl.translation of R,ICD-6) - 4156000500012 0.113 . 4156000500013 Also units "barns" are given in both articles for this 4156000500014 ratio - it's misprint. 4156000500015 ERR-ANALYS (DATA-ERR) Not specified. 4156000500016 STATUS (TABLE) Text, page 44, of R,ICD-6,42,1969. 4156000500017 (DEP,41560004) Derived from c-s. 4156000500018 ENDBIB 16 0 4156000500019 COMMON 1 3 4156000500020 EN-DUMMY 4156000500021 EV 4156000500022 0.0253 4156000500023 ENDCOMMON 3 0 4156000500024 DATA 2 1 4156000500025 DATA DATA-ERR 4156000500026 NO-DIM NO-DIM 4156000500027 0.118 0.029 4156000500028 ENDDATA 3 0 4156000500029 ENDSUBENT 28 0 4156000599999 ENDENTRY 5 0 4156099999999