ENTRY 40062 20220127 42044006200000001 SUBENT 40062001 20220127 42044006200100001 BIB 8 24 4006200100002 TITLE Cross sections and resonance integrals for capture and 4006200100003 fission in long-lived americium isotopes 4006200100004 AUTHOR (M.A.Bak, A.S.Krivokhatskii, K.A.Petrzhak, Yu.G.Petrov,4006200100005 Yu.F.Romanov, E.A.Shlyamin) 4006200100006 REFERENCE (J,AE,23,316,196710) Issue 4. 4006200100007 (J,SJA,23,1059,1967) Engl.transl.of J,AE,23,316,1967 4006200100008 #doi:10.1007/BF01120465 4006200100009 (R,YFI-5,49,1967) 4006200100010 (R,INDC(CCP)-1,51,1967) 4006200100011 INSTITUTE (4RUSRI) 4006200100012 FACILITY (REAC,4RUSRI) Thermal reactor WWR-M 4006200100013 COMMENT Exact meaning of cadmium neutron spectrum limit was not4006200100014 indicated. Cadmium neutron spectrum limit was supposed 4006200100015 to be equal to 0.4 eV 4006200100016 STATUS (TABLE) Table 2 of At.Energy,v.23,is.4,p.316,1967 . 4006200100017 = Table 1 of INDC(CCP)-1,p.51,1967 4006200100018 HISTORY (19710405C) 4006200100019 (20051101A) (M.M.) Correction of Reaction codes, 4006200100020 Subents 9-11 were added 4006200100021 (20130716A) Subent 003 was corrected. 4006200100022 Some misprints were corrected. 4006200100023 BIB information was updated. 4006200100024 (20220127A) Ref. INDC(CCP) was added. 4006200100025 Update for current rules and dictionaries. 4006200100026 ENDBIB 24 0 4006200100027 NOCOMMON 0 0 4006200100028 ENDSUBENT 27 0 4006200199999 SUBENT 40062002 20220127 42044006200200001 BIB 11 20 4006200200002 REACTION (95-AM-241(N,G)95-AM-242-G,,SIG) 4006200200003 INC-SOURCE (REAC) Samples were irradiated in neutron flux from 4006200200004 1.5E+13 to 1.0E+14 neutron/cm**2/sec. 4006200200005 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006200200006 0.1 % of Pu-239) on backing of beryllium or titanium 4006200200007 DECAY-DATA (95-AM-242-G,16.HR) 4006200200008 METHOD (ACTIV) For determination of thermal cross sections 4006200200009 samples were irradiated with cadmium cover and without 4006200200010 one. 4006200200011 Irradiation time was within 5-100 hours 4006200200012 DETECTOR (SI) 4006200200013 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 4006200200014 (93-NP-237(N,A)91-PA-234,,SIG) 4006200200015 They were used for measuring of neutron flux 4006200200016 RAD-DET (96-CM-242,A) 4006200200017 COMMENT In COMMON section EN-MIN and EN-MAX of incident 4006200200018 spectrum were given 4006200200019 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200200020 articles. 4006200200021 HISTORY (20220127A) PART-DET -> RAD-DET 4006200200022 ENDBIB 20 0 4006200200023 COMMON 2 3 4006200200024 EN-MIN EN-MAX 4006200200025 EV EV 4006200200026 0.0 4.0000E-01 4006200200027 ENDCOMMON 3 0 4006200200028 DATA 2 1 4006200200029 DATA DATA-ERR 4006200200030 B B 4006200200031 670. 60. 4006200200032 ENDDATA 3 0 4006200200033 ENDSUBENT 32 0 4006200299999 SUBENT 40062003 20220127 42044006200300001 BIB 12 33 4006200300002 REACTION (95-AM-241(N,G)95-AM-242-M,,SIG) 4006200300003 INC-SOURCE (REAC) Samples were irradiated in neutron flux from 4006200300004 1.5E+13 to 1.0E+14 neutron/cm**2/sec. Irradiation 4006200300005 time was within 5-100 hours. For determination 4006200300006 of Am-242-M quantity - 5.0E+7 neutron/cm**2/sec 4006200300007 neutron flux was used 4006200300008 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006200300009 0.1 % of Pu-239) on backing of beryllium or titanium 4006200300010 METHOD (ACTIV) For determination of thermal cross sections 4006200300011 samples were irradiated with cadmium cover and without 4006200300012 one 4006200300013 DETECTOR (FISCH) For determination of Am-242-M quantity 4006200300014 double fission chamber was used. 4006200300015 (SI) For samples alpha-activity measuring 4006200300016 MONITOR ((MONIT1)95-AM-242-M1(N,F),,SIG) 4006200300017 (79-AU-197(N,G)79-AU-198,,SIG) 4006200300018 For measuring of neutron flux gold 4006200300019 was used 4006200300020 (93-NP-237(N,A)91-PA-234,,SIG) 4006200300021 For measuring of neutron flux neptunium 4006200300022 was used 4006200300023 MONIT-REF ((MONIT1)12563002,K.Wolfsberg+,J,JNE/AB,20,588,1966) 4006200300024 ANALYSIS Am-241 capture c-s was measured by accumulated Am-242m 4006200300025 number defined by Am-242m thermal fission c-s . 4006200300026 PART-DET (FF) 4006200300027 (A) 4006200300028 COMMENT In COMMON section EN-MIN, EN-MAX of incident spectrum 4006200300029 and last fission cross section data of americium 242 4006200300030 in metastable state are given 4006200300031 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200300032 articles. 4006200300033 HISTORY (20130716A) AM-242-M1 -> AM-242-M was corrected in 4006200300034 Reaction according to the comment of N.Otsuka(NDS,IAEA)4006200300035 ENDBIB 33 0 4006200300036 COMMON 5 3 4006200300037 EN-MIN EN-MAX MONIT1 MONIT1-ERR EN-NRM 4006200300038 EV EV B B EV 4006200300039 0.0 4.0000E-01 7200. 300. 0.0253 4006200300040 ENDCOMMON 3 0 4006200300041 DATA 2 1 4006200300042 DATA DATA-ERR 4006200300043 B B 4006200300044 70. 5. 4006200300045 ENDDATA 3 0 4006200300046 ENDSUBENT 45 0 4006200399999 SUBENT 40062004 20220127 42044006200400001 BIB 8 17 4006200400002 REACTION (95-AM-242(N,F),,SIG) 4006200400003 INC-SOURCE (REAC) The samples were irradiated in 5.0E+7 neutron / 4006200400004 cm**2/sec neutron flux 4006200400005 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006200400006 0.1 % of Pu-239) on backing of beryllium or titanium 4006200400007 METHOD Counter ratio.For determination of thermal cross4006200400008 sections samples were irradiated with cadmium cover and4006200400009 without one 4006200400010 DETECTOR (FISCH) In experiments double ionization chamber 4006200400011 was used 4006200400012 (SI) For alpha-activity measuring 4006200400013 PART-DET (FF) 4006200400014 (A) 4006200400015 COMMENT In COMMON section EN-MIN and EN-MAX of incident 4006200400016 spectrum were given 4006200400017 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200400018 articles. 4006200400019 ENDBIB 17 0 4006200400020 COMMON 2 3 4006200400021 EN-MIN EN-MAX 4006200400022 EV EV 4006200400023 0.0 4.0000E-01 4006200400024 ENDCOMMON 3 0 4006200400025 DATA 2 1 4006200400026 DATA DATA-ERR 4006200400027 B B 4006200400028 2100. 200. 4006200400029 ENDDATA 3 0 4006200400030 ENDSUBENT 29 0 4006200499999 SUBENT 40062005 20220127 42044006200500001 BIB 10 20 4006200500002 REACTION (95-AM-243(N,G)95-AM-244,,SIG) 4006200500003 INC-SOURCE (REAC) Samples were irradiated in neutron flux from 4006200500004 1.5E+13 to 1.0E+14 neutrons/cm**2/sec. Irradiation 4006200500005 time was within 5-100 hours 4006200500006 SAMPLE A few micrograms of Am-241 and Am-243 mixture 4006200500007 (7.5 % of Am-241 and 91.5 %t of Am-243) 4006200500008 on backing of beryllium or titanium 4006200500009 METHOD (ACTIV) For determination of thermal cross sections 4006200500010 samples were irradiated with cadmium cover and without 4006200500011 one 4006200500012 DETECTOR Alpha spectrometer with silicon detector 4006200500013 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 4006200500014 (93-NP-237(N,A)91-PA-234,,SIG) 4006200500015 They are used for measuring neutron flux 4006200500016 RAD-DET (96-CM-244,A) 4006200500017 COMMENT In COMMON section EN-MIN and EN-MAX of incident 4006200500018 spectrum were given 4006200500019 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200500020 articles. 4006200500021 HISTORY (20220127A) PART-DET -> RAD-DET 4006200500022 ENDBIB 20 0 4006200500023 COMMON 2 3 4006200500024 EN-MIN EN-MAX 4006200500025 EV EV 4006200500026 0.0 4.0000E-01 4006200500027 ENDCOMMON 3 0 4006200500028 DATA 2 1 4006200500029 DATA DATA-ERR 4006200500030 B B 4006200500031 73. 6. 4006200500032 ENDDATA 3 0 4006200500033 ENDSUBENT 32 0 4006200599999 SUBENT 40062006 20220127 42044006200600001 BIB 7 15 4006200600002 REACTION (95-AM-241(N,G)95-AM-242-G,,RI) 4006200600003 INC-SOURCE (REAC) Samples were irradiated in neutron flux from 4006200600004 1.5E+13 to 1.0E+14 neutrons/cm**2/sec. 4006200600005 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006200600006 0.1 % of Pu-239) on backing of beryllium or titanium 4006200600007 METHOD Counter ratio. For relative measurement of 4006200600008 resonance integrals method of cadmium ratios was used 4006200600009 MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,RI) 4006200600010 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 4006200600011 COMMENT In Common Section EN-MIN of incident spectrum,capture 4006200600012 resonance integral and capture cross section of Au-197 4006200600013 were given. EN-MAX of incident spectrum was equal to 4006200600014 infinity 4006200600015 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200600016 articles. 4006200600017 ENDBIB 15 0 4006200600018 COMMON 5 3 4006200600019 EN-MIN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 4006200600020 EV B B B B 4006200600021 4.0000E-01 1.5580E+03 5.0000E+01 9.8800E+01 3.0000E-01 4006200600022 ENDCOMMON 3 0 4006200600023 DATA 2 1 4006200600024 DATA DATA-ERR 4006200600025 B B 4006200600026 2100. 200. 4006200600027 ENDDATA 3 0 4006200600028 ENDSUBENT 27 0 4006200699999 SUBENT 40062007 20220127 42044006200700001 BIB 8 16 4006200700002 REACTION (95-AM-241(N,G)95-AM-242-M,,RI) 4006200700003 INC-SOURCE (REAC) 4006200700004 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006200700005 0.1 % of Pu-239) on backing of beryllium or titanium 4006200700006 METHOD Counter ratio. For relative measurement of 4006200700007 resonance integrals, method of cadmium ratios was used 4006200700008 MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,RI) 4006200700009 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 4006200700010 ANALYSIS Resonance integral was determined using formula (25) 4006200700011 of Sov.J.At.Energy,v.23,p.1059,1967 4006200700012 COMMENT In Common Section EN-MIN of incident spectrum,capture 4006200700013 resonance integral and capture cross section of Au-197 4006200700014 were given. EN-MAX of incident spectrum was equal to 4006200700015 infinity 4006200700016 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200700017 articles. 4006200700018 ENDBIB 16 0 4006200700019 COMMON 5 3 4006200700020 EN-MIN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 4006200700021 EV B B B B 4006200700022 4.0000E-01 1558. 50. 98.8 0.3 4006200700023 ENDCOMMON 3 0 4006200700024 DATA 2 1 4006200700025 DATA DATA-ERR 4006200700026 B B 4006200700027 300. 30. 4006200700028 ENDDATA 3 0 4006200700029 ENDSUBENT 28 0 4006200799999 SUBENT 40062008 20220127 42044006200800001 BIB 8 18 4006200800002 REACTION (95-AM-243(N,G)95-AM-244,,RI) 4006200800003 INC-SOURCE (REAC) Samples were irradiated in neutron flux from 4006200800004 1.5E+13 to 1.0E+14 neutrons/cm**2/sec. 4006200800005 SAMPLE A few micrograms of Am-241 and Am-243 mixture 4006200800006 (7.5 % of Am-241 and 91.5 % of Am-243) 4006200800007 on backing of beryllium or titanium 4006200800008 METHOD Counter ratio. For relative measurement of 4006200800009 resonance integrals method of cadmium ratios was used 4006200800010 MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,RI) 4006200800011 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 4006200800012 ANALYSIS Resonance integral was determined using formula (25) 4006200800013 of Sov.J.At.Energy,v.23,p.1059,1967 4006200800014 COMMENT In common section EN-MIN incident spectrum and capture 4006200800015 resonance integral and capture cross section of Au-197 4006200800016 are given. EN-MAX incident spectrum was equal to 4006200800017 infinity 4006200800018 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200800019 articles. 4006200800020 ENDBIB 18 0 4006200800021 COMMON 5 3 4006200800022 EN-MIN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 4006200800023 EV B B B B 4006200800024 4.0000E-01 1558. 50. 98.8 0.3 4006200800025 ENDCOMMON 3 0 4006200800026 DATA 2 1 4006200800027 DATA DATA-ERR 4006200800028 B B 4006200800029 2300. 200. 4006200800030 ENDDATA 3 0 4006200800031 ENDSUBENT 30 0 4006200899999 SUBENT 40062009 20220127 42044006200900001 BIB 8 17 4006200900002 REACTION (95-AM-241(N,F),,SIG) 4006200900003 INC-SOURCE (REAC) The samples were irradiated by flux from 4006200900004 1.5E+13 to 1.0E+14 neutron/cm**2/sec. Irradiation 4006200900005 time was within 5-100 hours 4006200900006 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006200900007 0.1 % of Pu-239) on backing of beryllium or titanium 4006200900008 METHOD Counter ratio.For determination of thermal cross4006200900009 sections samples were irradiated with cadmium cover and4006200900010 without one 4006200900011 DETECTOR (FISCH) In experiments double ionization chamber 4006200900012 was used 4006200900013 PART-DET (FF) 4006200900014 (A) 4006200900015 COMMENT In common section EN-MIN and EN-MAX Of incident 4006200900016 spectrum were given 4006200900017 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200900018 articles. 4006200900019 ENDBIB 17 0 4006200900020 COMMON 2 3 4006200900021 EN-MIN EN-MAX 4006200900022 EV EV 4006200900023 0.0 4.0000E-01 4006200900024 ENDCOMMON 3 0 4006200900025 DATA 2 1 4006200900026 DATA DATA-ERR 4006200900027 B B 4006200900028 3.15 0.10 4006200900029 ENDDATA 3 0 4006200900030 ENDSUBENT 29 0 4006200999999 SUBENT 40062010 20220127 42044006201000001 BIB 9 19 4006201000002 REACTION (95-AM-241(N,F),,RI) 4006201000003 INC-SOURCE (REAC) The samples were irradiated by flux from 4006201000004 1.5E+13 to 1.0E+14 neutron/cm**2/sec. Irradiation 4006201000005 time was within 5-100 hours 4006201000006 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006201000007 0.1 % of Pu-239) on backing of beryllium or titanium 4006201000008 METHOD Counter ratio.For determination of thermal cross4006201000009 sections samples were irradiated with cadmium cover and4006201000010 without one 4006201000011 DETECTOR (FISCH) In experiments double ionization chamber 4006201000012 was used 4006201000013 PART-DET (FF) 4006201000014 (A) 4006201000015 MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,RI) 4006201000016 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 4006201000017 ANALYSIS Resonance integral was determined using formula (25) 4006201000018 of Sov.J.At.Energy,v.23,p.1059,1967 4006201000019 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006201000020 article 4006201000021 ENDBIB 19 0 4006201000022 COMMON 5 3 4006201000023 EN-MIN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 4006201000024 EV B B B B 4006201000025 4.0000E-01 1558. 50. 98.8 0.3 4006201000026 ENDCOMMON 3 0 4006201000027 DATA 2 1 4006201000028 DATA DATA-ERR 4006201000029 B B 4006201000030 21. 2. 4006201000031 ENDDATA 3 0 4006201000032 ENDSUBENT 31 0 4006201099999 SUBENT 40062011 20220127 42044006201100001 BIB 8 17 4006201100002 REACTION (95-AM-242(N,F),,RI) 4006201100003 INC-SOURCE (REAC) The samples were irradiated by flux 5.E+07 4006201100004 neutron/cm**2/sec. 4006201100005 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006201100006 0.1 % of Pu-239) on backing of beryllium or titanium 4006201100007 METHOD Counter ratio.For determination of thermal cross4006201100008 sections samples were irradiated with cadmium cover and4006201100009 without one 4006201100010 DETECTOR (FISCH) In experiments double ionization chamber 4006201100011 was used 4006201100012 (SI) For alpha-activity measuring 4006201100013 PART-DET (FF) 4006201100014 (A) 4006201100015 MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,RI) 4006201100016 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 4006201100017 ANALYSIS Resonance integral was determined using formula (25) 4006201100018 of Sov.J.At.Energy,v.23,p.1059,1967 4006201100019 ENDBIB 17 0 4006201100020 COMMON 5 3 4006201100021 EN-MIN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 4006201100022 EV B B B B 4006201100023 4.0000E-01 1558. 50. 98.8 0.3 4006201100024 ENDCOMMON 3 0 4006201100025 DATA 1 1 4006201100026 DATA-MAX 4006201100027 B 4006201100028 300. 4006201100029 ENDDATA 3 0 4006201100030 ENDSUBENT 29 0 4006201199999 ENDENTRY 11 0 4006299999999