ENTRY 40062 20220127 420440062 0 1 SUBENT 40062001 20220127 420440062 1 1 BIB 8 24 40062 1 2 TITLE Cross sections and resonance integrals for capture and 40062 1 3 fission in long-lived americium isotopes 40062 1 4 AUTHOR (M.A.Bak, A.S.Krivokhatskii, K.A.Petrzhak, Yu.G.Petrov,40062 1 5 Yu.F.Romanov, E.A.Shlyamin) 40062 1 6 REFERENCE (J,AE,23,316,196710) Issue 4. 40062 1 7 (J,SJA,23,1059,1967) Engl.transl.of J,AE,23,316,1967 40062 1 8 #doi:10.1007/BF01120465 40062 1 9 (R,YFI-5,49,1967) 40062 1 10 (R,INDC(CCP)-1,51,1967) 40062 1 11 INSTITUTE (4RUSRI) 40062 1 12 FACILITY (REAC,4RUSRI) Thermal reactor WWR-M 40062 1 13 COMMENT Exact meaning of cadmium neutron spectrum limit was not40062 1 14 indicated. Cadmium neutron spectrum limit was supposed 40062 1 15 to be equal to 0.4 eV 40062 1 16 STATUS (TABLE) Table 2 of At.Energy,v.23,is.4,p.316,1967 . 40062 1 17 = Table 1 of INDC(CCP)-1,p.51,1967 40062 1 18 HISTORY (19710405C) 40062 1 19 (20051101A) (M.M.) Correction of Reaction codes, 40062 1 20 Subents 9-11 were added 40062 1 21 (20130716A) Subent 003 was corrected. 40062 1 22 Some misprints were corrected. 40062 1 23 BIB information was updated. 40062 1 24 (20220127A) Ref. INDC(CCP) was added. 40062 1 25 Update for current rules and dictionaries. 40062 1 26 ENDBIB 24 0 40062 1 27 NOCOMMON 0 0 40062 1 28 ENDSUBENT 27 0 40062 199999 SUBENT 40062002 20220127 420440062 2 1 BIB 11 20 40062 2 2 REACTION (95-AM-241(N,G)95-AM-242-G,,SIG) 40062 2 3 INC-SOURCE (REAC) Samples were irradiated in neutron flux from 40062 2 4 1.5E+13 to 1.0E+14 neutron/cm**2/sec. 40062 2 5 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 40062 2 6 0.1 % of Pu-239) on backing of beryllium or titanium 40062 2 7 DECAY-DATA (95-AM-242-G,16.HR) 40062 2 8 METHOD (ACTIV) For determination of thermal cross sections 40062 2 9 samples were irradiated with cadmium cover and without 40062 2 10 one. 40062 2 11 Irradiation time was within 5-100 hours 40062 2 12 DETECTOR (SI) 40062 2 13 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 40062 2 14 (93-NP-237(N,A)91-PA-234,,SIG) 40062 2 15 They were used for measuring of neutron flux 40062 2 16 RAD-DET (96-CM-242,A) 40062 2 17 COMMENT In COMMON section EN-MIN and EN-MAX of incident 40062 2 18 spectrum were given 40062 2 19 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 40062 2 20 articles. 40062 2 21 HISTORY (20220127A) PART-DET -> RAD-DET 40062 2 22 ENDBIB 20 0 40062 2 23 COMMON 2 3 40062 2 24 EN-MIN EN-MAX 40062 2 25 EV EV 40062 2 26 0.0 4.0000E-01 40062 2 27 ENDCOMMON 3 0 40062 2 28 DATA 2 1 40062 2 29 DATA DATA-ERR 40062 2 30 B B 40062 2 31 670. 60. 40062 2 32 ENDDATA 3 0 40062 2 33 ENDSUBENT 32 0 40062 299999 SUBENT 40062003 20220127 420440062 3 1 BIB 12 33 40062 3 2 REACTION (95-AM-241(N,G)95-AM-242-M,,SIG) 40062 3 3 INC-SOURCE (REAC) Samples were irradiated in neutron flux from 40062 3 4 1.5E+13 to 1.0E+14 neutron/cm**2/sec. Irradiation 40062 3 5 time was within 5-100 hours. For determination 40062 3 6 of Am-242-M quantity - 5.0E+7 neutron/cm**2/sec 40062 3 7 neutron flux was used 40062 3 8 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 40062 3 9 0.1 % of Pu-239) on backing of beryllium or titanium 40062 3 10 METHOD (ACTIV) For determination of thermal cross sections 40062 3 11 samples were irradiated with cadmium cover and without 40062 3 12 one 40062 3 13 DETECTOR (FISCH) For determination of Am-242-M quantity 40062 3 14 double fission chamber was used. 40062 3 15 (SI) For samples alpha-activity measuring 40062 3 16 MONITOR ((MONIT1)95-AM-242-M1(N,F),,SIG) 40062 3 17 (79-AU-197(N,G)79-AU-198,,SIG) 40062 3 18 For measuring of neutron flux gold 40062 3 19 was used 40062 3 20 (93-NP-237(N,A)91-PA-234,,SIG) 40062 3 21 For measuring of neutron flux neptunium 40062 3 22 was used 40062 3 23 MONIT-REF ((MONIT1)12563002,K.Wolfsberg+,J,JNE/AB,20,588,1966) 40062 3 24 ANALYSIS Am-241 capture c-s was measured by accumulated Am-242m 40062 3 25 number defined by Am-242m thermal fission c-s . 40062 3 26 PART-DET (FF) 40062 3 27 (A) 40062 3 28 COMMENT In COMMON section EN-MIN, EN-MAX of incident spectrum 40062 3 29 and last fission cross section data of americium 242 40062 3 30 in metastable state are given 40062 3 31 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 40062 3 32 articles. 40062 3 33 HISTORY (20130716A) AM-242-M1 -> AM-242-M was corrected in 40062 3 34 Reaction according to the comment of N.Otsuka(NDS,IAEA)40062 3 35 ENDBIB 33 0 40062 3 36 COMMON 5 3 40062 3 37 EN-MIN EN-MAX MONIT1 MONIT1-ERR EN-NRM 40062 3 38 EV EV B B EV 40062 3 39 0.0 4.0000E-01 7200. 300. 0.0253 40062 3 40 ENDCOMMON 3 0 40062 3 41 DATA 2 1 40062 3 42 DATA DATA-ERR 40062 3 43 B B 40062 3 44 70. 5. 40062 3 45 ENDDATA 3 0 40062 3 46 ENDSUBENT 45 0 40062 399999 SUBENT 40062004 20220127 420440062 4 1 BIB 8 17 40062 4 2 REACTION (95-AM-242(N,F),,SIG) 40062 4 3 INC-SOURCE (REAC) The samples were irradiated in 5.0E+7 neutron / 40062 4 4 cm**2/sec neutron flux 40062 4 5 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 40062 4 6 0.1 % of Pu-239) on backing of beryllium or titanium 40062 4 7 METHOD Counter ratio.For determination of thermal cross40062 4 8 sections samples were irradiated with cadmium cover and40062 4 9 without one 40062 4 10 DETECTOR (FISCH) In experiments double ionization chamber 40062 4 11 was used 40062 4 12 (SI) For alpha-activity measuring 40062 4 13 PART-DET (FF) 40062 4 14 (A) 40062 4 15 COMMENT In COMMON section EN-MIN and EN-MAX of incident 40062 4 16 spectrum were given 40062 4 17 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 40062 4 18 articles. 40062 4 19 ENDBIB 17 0 40062 4 20 COMMON 2 3 40062 4 21 EN-MIN EN-MAX 40062 4 22 EV EV 40062 4 23 0.0 4.0000E-01 40062 4 24 ENDCOMMON 3 0 40062 4 25 DATA 2 1 40062 4 26 DATA DATA-ERR 40062 4 27 B B 40062 4 28 2100. 200. 40062 4 29 ENDDATA 3 0 40062 4 30 ENDSUBENT 29 0 40062 499999 SUBENT 40062005 20220127 420440062 5 1 BIB 10 20 40062 5 2 REACTION (95-AM-243(N,G)95-AM-244,,SIG) 40062 5 3 INC-SOURCE (REAC) Samples were irradiated in neutron flux from 40062 5 4 1.5E+13 to 1.0E+14 neutrons/cm**2/sec. Irradiation 40062 5 5 time was within 5-100 hours 40062 5 6 SAMPLE A few micrograms of Am-241 and Am-243 mixture 40062 5 7 (7.5 % of Am-241 and 91.5 %t of Am-243) 40062 5 8 on backing of beryllium or titanium 40062 5 9 METHOD (ACTIV) For determination of thermal cross sections 40062 5 10 samples were irradiated with cadmium cover and without 40062 5 11 one 40062 5 12 DETECTOR Alpha spectrometer with silicon detector 40062 5 13 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 40062 5 14 (93-NP-237(N,A)91-PA-234,,SIG) 40062 5 15 They are used for measuring neutron flux 40062 5 16 RAD-DET (96-CM-244,A) 40062 5 17 COMMENT In COMMON section EN-MIN and EN-MAX of incident 40062 5 18 spectrum were given 40062 5 19 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 40062 5 20 articles. 40062 5 21 HISTORY (20220127A) PART-DET -> RAD-DET 40062 5 22 ENDBIB 20 0 40062 5 23 COMMON 2 3 40062 5 24 EN-MIN EN-MAX 40062 5 25 EV EV 40062 5 26 0.0 4.0000E-01 40062 5 27 ENDCOMMON 3 0 40062 5 28 DATA 2 1 40062 5 29 DATA DATA-ERR 40062 5 30 B B 40062 5 31 73. 6. 40062 5 32 ENDDATA 3 0 40062 5 33 ENDSUBENT 32 0 40062 599999 SUBENT 40062006 20220127 420440062 6 1 BIB 7 15 40062 6 2 REACTION (95-AM-241(N,G)95-AM-242-G,,RI) 40062 6 3 INC-SOURCE (REAC) Samples were irradiated in neutron flux from 40062 6 4 1.5E+13 to 1.0E+14 neutrons/cm**2/sec. 40062 6 5 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 40062 6 6 0.1 % of Pu-239) on backing of beryllium or titanium 40062 6 7 METHOD Counter ratio. For relative measurement of 40062 6 8 resonance integrals method of cadmium ratios was used 40062 6 9 MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,RI) 40062 6 10 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 40062 6 11 COMMENT In Common Section EN-MIN of incident spectrum,capture 40062 6 12 resonance integral and capture cross section of Au-197 40062 6 13 were given. EN-MAX of incident spectrum was equal to 40062 6 14 infinity 40062 6 15 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 40062 6 16 articles. 40062 6 17 ENDBIB 15 0 40062 6 18 COMMON 5 3 40062 6 19 EN-MIN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 40062 6 20 EV B B B B 40062 6 21 4.0000E-01 1.5580E+03 5.0000E+01 9.8800E+01 3.0000E-01 40062 6 22 ENDCOMMON 3 0 40062 6 23 DATA 2 1 40062 6 24 DATA DATA-ERR 40062 6 25 B B 40062 6 26 2100. 200. 40062 6 27 ENDDATA 3 0 40062 6 28 ENDSUBENT 27 0 40062 699999 SUBENT 40062007 20220127 420440062 7 1 BIB 8 16 40062 7 2 REACTION (95-AM-241(N,G)95-AM-242-M,,RI) 40062 7 3 INC-SOURCE (REAC) 40062 7 4 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 40062 7 5 0.1 % of Pu-239) on backing of beryllium or titanium 40062 7 6 METHOD Counter ratio. For relative measurement of 40062 7 7 resonance integrals, method of cadmium ratios was used 40062 7 8 MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,RI) 40062 7 9 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 40062 7 10 ANALYSIS Resonance integral was determined using formula (25) 40062 7 11 of Sov.J.At.Energy,v.23,p.1059,1967 40062 7 12 COMMENT In Common Section EN-MIN of incident spectrum,capture 40062 7 13 resonance integral and capture cross section of Au-197 40062 7 14 were given. EN-MAX of incident spectrum was equal to 40062 7 15 infinity 40062 7 16 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 40062 7 17 articles. 40062 7 18 ENDBIB 16 0 40062 7 19 COMMON 5 3 40062 7 20 EN-MIN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 40062 7 21 EV B B B B 40062 7 22 4.0000E-01 1558. 50. 98.8 0.3 40062 7 23 ENDCOMMON 3 0 40062 7 24 DATA 2 1 40062 7 25 DATA DATA-ERR 40062 7 26 B B 40062 7 27 300. 30. 40062 7 28 ENDDATA 3 0 40062 7 29 ENDSUBENT 28 0 40062 799999 SUBENT 40062008 20220127 420440062 8 1 BIB 8 18 40062 8 2 REACTION (95-AM-243(N,G)95-AM-244,,RI) 40062 8 3 INC-SOURCE (REAC) Samples were irradiated in neutron flux from 40062 8 4 1.5E+13 to 1.0E+14 neutrons/cm**2/sec. 40062 8 5 SAMPLE A few micrograms of Am-241 and Am-243 mixture 40062 8 6 (7.5 % of Am-241 and 91.5 % of Am-243) 40062 8 7 on backing of beryllium or titanium 40062 8 8 METHOD Counter ratio. For relative measurement of 40062 8 9 resonance integrals method of cadmium ratios was used 40062 8 10 MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,RI) 40062 8 11 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 40062 8 12 ANALYSIS Resonance integral was determined using formula (25) 40062 8 13 of Sov.J.At.Energy,v.23,p.1059,1967 40062 8 14 COMMENT In common section EN-MIN incident spectrum and capture 40062 8 15 resonance integral and capture cross section of Au-197 40062 8 16 are given. EN-MAX incident spectrum was equal to 40062 8 17 infinity 40062 8 18 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 40062 8 19 articles. 40062 8 20 ENDBIB 18 0 40062 8 21 COMMON 5 3 40062 8 22 EN-MIN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 40062 8 23 EV B B B B 40062 8 24 4.0000E-01 1558. 50. 98.8 0.3 40062 8 25 ENDCOMMON 3 0 40062 8 26 DATA 2 1 40062 8 27 DATA DATA-ERR 40062 8 28 B B 40062 8 29 2300. 200. 40062 8 30 ENDDATA 3 0 40062 8 31 ENDSUBENT 30 0 40062 899999 SUBENT 40062009 20220127 420440062 9 1 BIB 8 17 40062 9 2 REACTION (95-AM-241(N,F),,SIG) 40062 9 3 INC-SOURCE (REAC) The samples were irradiated by flux from 40062 9 4 1.5E+13 to 1.0E+14 neutron/cm**2/sec. Irradiation 40062 9 5 time was within 5-100 hours 40062 9 6 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 40062 9 7 0.1 % of Pu-239) on backing of beryllium or titanium 40062 9 8 METHOD Counter ratio.For determination of thermal cross40062 9 9 sections samples were irradiated with cadmium cover and40062 9 10 without one 40062 9 11 DETECTOR (FISCH) In experiments double ionization chamber 40062 9 12 was used 40062 9 13 PART-DET (FF) 40062 9 14 (A) 40062 9 15 COMMENT In common section EN-MIN and EN-MAX Of incident 40062 9 16 spectrum were given 40062 9 17 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 40062 9 18 articles. 40062 9 19 ENDBIB 17 0 40062 9 20 COMMON 2 3 40062 9 21 EN-MIN EN-MAX 40062 9 22 EV EV 40062 9 23 0.0 4.0000E-01 40062 9 24 ENDCOMMON 3 0 40062 9 25 DATA 2 1 40062 9 26 DATA DATA-ERR 40062 9 27 B B 40062 9 28 3.15 0.10 40062 9 29 ENDDATA 3 0 40062 9 30 ENDSUBENT 29 0 40062 999999 SUBENT 40062010 20220127 420440062 10 1 BIB 9 19 40062 10 2 REACTION (95-AM-241(N,F),,RI) 40062 10 3 INC-SOURCE (REAC) The samples were irradiated by flux from 40062 10 4 1.5E+13 to 1.0E+14 neutron/cm**2/sec. Irradiation 40062 10 5 time was within 5-100 hours 40062 10 6 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 40062 10 7 0.1 % of Pu-239) on backing of beryllium or titanium 40062 10 8 METHOD Counter ratio.For determination of thermal cross40062 10 9 sections samples were irradiated with cadmium cover and40062 10 10 without one 40062 10 11 DETECTOR (FISCH) In experiments double ionization chamber 40062 10 12 was used 40062 10 13 PART-DET (FF) 40062 10 14 (A) 40062 10 15 MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,RI) 40062 10 16 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 40062 10 17 ANALYSIS Resonance integral was determined using formula (25) 40062 10 18 of Sov.J.At.Energy,v.23,p.1059,1967 40062 10 19 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 40062 10 20 article 40062 10 21 ENDBIB 19 0 40062 10 22 COMMON 5 3 40062 10 23 EN-MIN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 40062 10 24 EV B B B B 40062 10 25 4.0000E-01 1558. 50. 98.8 0.3 40062 10 26 ENDCOMMON 3 0 40062 10 27 DATA 2 1 40062 10 28 DATA DATA-ERR 40062 10 29 B B 40062 10 30 21. 2. 40062 10 31 ENDDATA 3 0 40062 10 32 ENDSUBENT 31 0 40062 1099999 SUBENT 40062011 20220127 420440062 11 1 BIB 8 17 40062 11 2 REACTION (95-AM-242(N,F),,RI) 40062 11 3 INC-SOURCE (REAC) The samples were irradiated by flux 5.E+07 40062 11 4 neutron/cm**2/sec. 40062 11 5 SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 40062 11 6 0.1 % of Pu-239) on backing of beryllium or titanium 40062 11 7 METHOD Counter ratio.For determination of thermal cross40062 11 8 sections samples were irradiated with cadmium cover and40062 11 9 without one 40062 11 10 DETECTOR (FISCH) In experiments double ionization chamber 40062 11 11 was used 40062 11 12 (SI) For alpha-activity measuring 40062 11 13 PART-DET (FF) 40062 11 14 (A) 40062 11 15 MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,RI) 40062 11 16 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 40062 11 17 ANALYSIS Resonance integral was determined using formula (25) 40062 11 18 of Sov.J.At.Energy,v.23,p.1059,1967 40062 11 19 ENDBIB 17 0 40062 11 20 COMMON 5 3 40062 11 21 EN-MIN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 40062 11 22 EV B B B B 40062 11 23 4.0000E-01 1558. 50. 98.8 0.3 40062 11 24 ENDCOMMON 3 0 40062 11 25 DATA 1 1 40062 11 26 DATA-MAX 40062 11 27 B 40062 11 28 300. 40062 11 29 ENDDATA 3 0 40062 11 30 ENDSUBENT 29 0 40062 1199999 ENDENTRY 11 0 4006299999999