ENTRY 20868 20150721 22432086800000001 SUBENT 20868001 20150721 22432086800100001 BIB 11 38 2086800100002 INSTITUTE (2NEDAMS) 2086800100003 REFERENCE ((R,INDC(NED)-3,1970)=(R,INDC-430,1970)) Main ref. 2086800100004 thesis materials are presented in report. 2086800100005 (J,JNE,25,457,197109) 2086800100006 (J,JNE,25,459,197109) 2086800100007 (P,EANDC(E)-140,197108) 2086800100008 (P,EANDC(E)-127,197004) 2086800100009 AUTHOR (H.Pauw) 2086800100010 TITLE Energy spectra of radioactive neutron sources 2086800100011 METHOD (ACTIV) Activation for the indium and gold measurements2086800100012 DETECTOR (NAICR) 3. x 3. inch NaI(Tl) well-type crystal for 2086800100013 the indium and gold measurements. 2086800100014 (TRD) Makrofol (polycarbonate foil) track detector 2086800100015 for fission fragments. 2086800100016 PART-DET (DG) Decay gammas for the indium and gold measurements 2086800100017 (FF) Fission fragments. 2086800100018 STATUS (TABLE) .Data taken from INDC-430,1970. 2086800100019 CORRECTION .Corrections for self-absorption of gamma-rays in gold 2086800100020 sample, for anisotropy of the neutron source, for 2086800100021 detection efficiency, for decay or number of tracks, 2086800100022 and for effective distance between neutron source 2086800100023 and sample have been applied. 2086800100024 .In the measurements with the Sb-124+Be neutron source 2086800100025 on gold, indium and plutonium a factor of 0.95 +-0.02 2086800100026 was applied to correct for the 380 keV neutrons. 2086800100027 ERR-ANALYS (DATA-ERR) .No information given. 2086800100028 HISTORY (19790409C) CN. 2086800100029 (19790518E) 2086800100030 (20120719A) SD: Updated to new date formats,lower case.2086800100031 Corrections according last EXFOR rules and Dict. 2086800100032 (20150721A) SD: Ref. INDC-430,1970 was added. SAMPLE 2086800100033 and INC-SOURCE moved from Subent 001 to Subents 002-28.2086800100034 INC-SPECT deleted from Subents 002-028 (full info is 2086800100035 given in INC-SOURCE). Multiple reaction formalism was 2086800100036 used in Subents 002-010, 012-015,017,022,026. 2086800100037 Subents 003,011,016 were splitted following INC-SOURCE.2086800100038 EN-DUMMY -> KT-DUMMY in all Subents where Cf-252 is 2086800100039 neutron source. INC-SOURCE update in Subents 002-0028. 2086800100040 ENDBIB 38 0 2086800100041 NOCOMMON 0 0 2086800100042 ENDSUBENT 41 0 2086800199999 SUBENT 20868002 20150721 22432086800200001 BIB 7 29 2086800200002 REACTION 1(49-IN-115(N,G)49-IN-116-M1+M2,,SIG,,SPA) 2086800200003 2(49-IN-115(N,G)49-IN-116-M1+M2,,SIG,,SPA) 2086800200004 3(49-IN-115(N,G)49-IN-116-M1+M2,,SIG,,SPA) 2086800200005 4(49-IN-115(N,G)49-IN-116-M1+M2,,SIG,,SPA) 2086800200006 INC-SOURCE1(AM-BE) Am-241+Be, pelleted mixture of Am-oxide + Be in2086800200007 stainless steel container; 48.5 x 22.4 mm (h x diam.); 2086800200008 amount of radioactive material - 3Ci; neutron emission 2086800200009 rate 8.6 x 10**6 n/sec; anisotropy factor 1.039. 2086800200010 2(PU-BE) Pu-239+Be, alloy of Pu + Be in tantalum or 2086800200011 stainless steel container; 52.3 x 39.5 mm (h x diam.); 2086800200012 amount of radioactive material - 5Ci; neutron emission2086800200013 rate 1.0 x 10**7n/sec; anisotropy factor 1.052. 2086800200014 3(RA-BE) Ra-226+Be, pressed mechanical mixture of Ra+Be 2086800200015 in monel or platinum container; 15.4x15.0mm(h x diam.);2086800200016 amount of radioactive material - 0.1Ci; neutron 2086800200017 emission rate 1.5x10**6 n/sec;anisotropy factor 1.014.2086800200018 4(CM-BE) Cm-242+Be, pelleted mixture of Cm-oxide + Be in2086800200019 stainless steel container; 19.4 x 17.4 mm (h x diam.); 2086800200020 amount of radioactive material - 1Ci; neutron emission2086800200021 rate 3.5 x 10**6 n/sec; anisotropy factor 1.012. 2086800200022 DECAY-DATA (49-IN-116-M1,54.13MIN,DG,1293.,0.837) 2086800200023 SAMPLE .Natural indium sphere 1 cm in diameter. 2086800200024 FLAG (1.) detector without surrounding by B-10 sphere 2086800200025 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086800200026 STATUS (TABLE) .Decay data taken from text, cross section 2086800200027 data from table VI.1 of INDC-430,1970. 2086800200028 HISTORY (20120719A) SD: 49-IN-116-M -> 49-IN-116-M1+M2 in 2086800200029 REACTION code and DECAY-DATA. Multiple reaction 2086800200030 formalism applied. Description of FLAG was changed. 2086800200031 ENDBIB 29 0 2086800200032 COMMON 1 3 2086800200033 EN-DUMMY 2086800200034 MEV 2086800200035 4.5 2086800200036 ENDCOMMON 3 0 2086800200037 DATA 9 2 2086800200038 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32086800200039 DATA 4DATA-ERR 4FLAG 2086800200040 MB MB MB MB MB MB 2086800200041 MB MB NO-DIM 2086800200042 70.6 4.0 83.4 3.1 87.9 3.92086800200043 74.7 2.7 1. 2086800200044 60.7 2.6 77.0 3.0 82.3 3.72086800200045 67.9 2.5 2. 2086800200046 ENDDATA 8 0 2086800200047 ENDSUBENT 46 0 2086800299999 SUBENT 20868003 20150721 22432086800300001 BIB 7 18 2086800300002 REACTION (49-IN-115(N,G)49-IN-116-M1+M2,,SIG,,FIS) 2086800300003 INC-SOURCE Mock-Fission (Po-210+Be+B+F) neutron sources. 2086800300004 Mock-Fission source in stainless steel container; 2086800300005 17.0 x 15.0 mm (h x diam.); amount of radioactive 2086800300006 material - 1Ci. 2086800300007 Mock-Fission neutron source is a mixture of Po, Be, B, 2086800300008 F (and Li) in the correct proportions constitutes a 2086800300009 neutron source, the spectrum of which resembles an 2086800300010 uranium fission spectrum. 2086800300011 DECAY-DATA (49-IN-116-M1,54.13MIN,DG,1293.,0.837) 2086800300012 SAMPLE .Natural indium sphere 1 cm in diameter. 2086800300013 FLAG (1.) detector without surrounding by B-10 sphere 2086800300014 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086800300015 STATUS (TABLE) .Decay data taken from text, cross section 2086800300016 data from table VI.1 of INDC-430,1970 2086800300017 HISTORY (20120719A) SD: 49-IN-116-M -> 49-IN-116-M1+M2 in 2086800300018 REACTION code and DECAY-DATA. Description of FLAG was 2086800300019 changed. Part of data were moved to Subent 029. 2086800300020 ENDBIB 18 0 2086800300021 COMMON 1 3 2086800300022 EN-DUMMY 2086800300023 MEV 2086800300024 1.5 2086800300025 ENDCOMMON 3 0 2086800300026 DATA 3 2 2086800300027 DATA DATA-ERR FLAG 2086800300028 MB MB NO-DIM 2086800300029 93.0 6.3 2.0 2086800300030 96.4 8.4 1.0 2086800300031 ENDDATA 4 0 2086800300032 ENDSUBENT 31 0 2086800399999 SUBENT 20868004 20150721 22432086800400001 BIB 7 18 2086800400002 REACTION 1(49-IN-115(N,G)49-IN-116-M1+M2,,SIG) 2086800400003 2(49-IN-115(N,G)49-IN-116-M1+M2,,SIG) 2086800400004 INC-SOURCE1Sb-124+Be in Al-container; anisotropy factor 1.030. 2086800400005 2Sb-124+Be in Ti-container; anisotropy factor 1.105. 2086800400006 Sb-124+Be neutron source in aluminium or titanium 2086800400007 container; 36.0 x 23.0 mm (h x diam.); amount of 2086800400008 radioactive material - 1Ci; neutron 2086800400009 emission rate 1.0 x 10**6 n/sec; anisotropy 2086800400010 factor 1.030. 2086800400011 DECAY-DATA (49-IN-116-M1,54.13MIN,DG,1293.,0.837) 2086800400012 SAMPLE .Natural indium sphere 1 cm in diameter. 2086800400013 FLAG (1.) detector without surrounding by B-10 sphere 2086800400014 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086800400015 STATUS (TABLE) .Decay data taken from text, cross section 2086800400016 data from table VI.1 of INDC-430,1970 2086800400017 HISTORY (19860808A)HH reaction string corrected 2086800400018 (20120719A) SD: Multiple reaction formalism applied. 2086800400019 Description of FLAG was changed. 2086800400020 ENDBIB 18 0 2086800400021 COMMON 1 3 2086800400022 EN-RSL 2086800400023 KEV 2086800400024 1. 2086800400025 ENDCOMMON 3 0 2086800400026 DATA 6 4 2086800400027 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2FLAG 2086800400028 KEV MB MB MB MB NO-DIM 2086800400029 21.0 640.0 40.0 1.02086800400030 21.0 325.0 20.0 2.02086800400031 22.0 550.0 50.0 1.02086800400032 22.0 315.0 30.0 2.02086800400033 ENDDATA 6 0 2086800400034 ENDSUBENT 33 0 2086800499999 SUBENT 20868005 20150721 22432086800500001 BIB 7 17 2086800500002 REACTION (49-IN-115(N,G)49-IN-116-M1+M2,,SIG,,SPA) 2086800500003 INC-SOURCE Am-241+Al in Al-container neutron source. 2086800500004 Am-241+Al neutron source in aluminium container; 2086800500005 72.0 x 12.0 mm (h x diam.); amount of radioactive 2086800500006 material - 5Ci; neutron emission rate 2086800500007 4.4 x 10**4 n/sec; anisotropy factor 1.042. 2086800500008 The source consists of a homogeneous mixture of A1 2086800500009 and 241AmO(2). 2086800500010 DECAY-DATA (49-IN-116-M1,54.13MIN,DG,1293.,0.837) 2086800500011 SAMPLE .Natural indium sphere 1 cm in diameter. 2086800500012 FLAG (1.) detector without surrounding by B-10 sphere 2086800500013 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086800500014 STATUS (TABLE) .Decay data taken from text, cross section 2086800500015 data from table VI.1 of INDC-430,1970 2086800500016 HISTORY (20120719A) SD: 49-IN-116-M1 -> 49-IN-116-M1+M2 in 2086800500017 REACTION code and DECAY-DATA. Description of FLAG was 2086800500018 changed. 2086800500019 ENDBIB 17 0 2086800500020 COMMON 1 3 2086800500021 EN-DUMMY 2086800500022 KEV 2086800500023 500. 2086800500024 ENDCOMMON 3 0 2086800500025 DATA 3 2 2086800500026 DATA DATA-ERR FLAG 2086800500027 MB MB NO-DIM 2086800500028 152.0 11.0 2.0 2086800500029 162.0 6.0 1.0 2086800500030 ENDDATA 4 0 2086800500031 ENDSUBENT 30 0 2086800599999 SUBENT 20868006 20150721 22432086800600001 BIB 7 17 2086800600002 REACTION (49-IN-115(N,G)49-IN-116-M1+M2,,SIG,,SPA) 2086800600003 INC-SOURCE .One Am-241+Li in Li-container neutron source. 2086800600004 Am-241+Li neutron source in stainless steel container; 2086800600005 31.0 x 22.4 mm (h x diam.); amount of radioactive 2086800600006 material - 1.5Ci; neutron emission rate 2086800600007 6.7 x 10**4 n/sec; anisotropy factor 1.023. 2086800600008 AmLi neutron source consists of an intimate 2086800600009 mixture of Li and 241AmO(2). 2086800600010 DECAY-DATA (49-IN-116-M1,54.13MIN,DG,1293.,0.837) 2086800600011 SAMPLE .Natural indium sphere 1 cm in diameter. 2086800600012 FLAG (1.) detector without surrounding by B-10 sphere 2086800600013 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086800600014 STATUS (TABLE) .Decay data taken from text, cross section 2086800600015 data from table VI.1 of INDC-430,1970 2086800600016 HISTORY (20120719A) SD: 49-IN-116-M -> 49-IN-116-M1+M2 in 2086800600017 REACTION code and DECAY-DATA. Description of FLAG was 2086800600018 changed. 2086800600019 ENDBIB 17 0 2086800600020 COMMON 1 3 2086800600021 EN-DUMMY 2086800600022 KEV 2086800600023 100. 2086800600024 ENDCOMMON 3 0 2086800600025 DATA 3 2 2086800600026 DATA DATA-ERR FLAG 2086800600027 MB MB NO-DIM 2086800600028 167. 13. 2. 2086800600029 264. 16. 1. 2086800600030 ENDDATA 4 0 2086800600031 ENDSUBENT 30 0 2086800699999 SUBENT 20868007 20150721 22432086800700001 BIB 7 28 2086800700002 REACTION 1(49-IN-115(N,INL)49-IN-115-M,,SIG,,SPA) 2086800700003 2(49-IN-115(N,INL)49-IN-115-M,,SIG,,SPA) 2086800700004 3(49-IN-115(N,INL)49-IN-115-M,,SIG,,SPA) 2086800700005 4(49-IN-115(N,INL)49-IN-115-M,,SIG,,SPA) 2086800700006 INC-SOURCE1(AM-BE) Am-241+Be, pelleted mixture of Am-oxide + Be in2086800700007 stainless steel container; 48.5 x 22.4 mm (h x diam.); 2086800700008 amount of radioactive material - 3Ci; neutron emission 2086800700009 rate 8.6 x 10**6 n/sec; anisotropy factor 1.039. 2086800700010 2(PU-BE) Pu-239+Be, alloy of Pu + Be in tantalum or 2086800700011 stainless steel container; 52.3 x 39.5 mm (h x diam.); 2086800700012 amount of radioactive material - 5Ci; neutron emission2086800700013 rate 1.0 x 10**7n/sec; anisotropy factor 1.052. 2086800700014 3(RA-BE) Ra-226+Be, pressed mechanical mixture of Ra+Be 2086800700015 in monel or platinum container; 15.4x15.0mm(h x diam.);2086800700016 amount of radioactive material - 0.1Ci; neutron 2086800700017 emission rate 1.5x10**6 n/sec; anisotropy factor 1.0142086800700018 4(CM-BE) Cm-242+Be, pelleted mixture of Cm-oxide + Be in2086800700019 stainless steel container; 19.4 x 17.4 mm (h x diam.); 2086800700020 amount of radioactive material - 1Ci; neutron emission2086800700021 rate 3.5 x 10**6 n/sec; anisotropy factor 1.012. 2086800700022 DECAY-DATA (49-IN-115-M,4.50HR,DG,335.,0.500) 2086800700023 SAMPLE .Natural indium sphere 1 cm in diameter. 2086800700024 FLAG (1.) detector without surrounding by B-10 sphere 2086800700025 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086800700026 STATUS (TABLE) .Decay data taken from text, cross section 2086800700027 data from table VI.1 of INDC-430,1970 2086800700028 HISTORY (20120719A) SD: Multiple reaction formalism applied. 2086800700029 Description of FLAG was changed. 2086800700030 ENDBIB 28 0 2086800700031 COMMON 1 3 2086800700032 EN-DUMMY 2086800700033 MEV 2086800700034 4.5 2086800700035 ENDCOMMON 3 0 2086800700036 DATA 9 2 2086800700037 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32086800700038 DATA 4DATA-ERR 4FLAG 2086800700039 MB MB MB MB MB MB 2086800700040 MB MB NO-DIM 2086800700041 272. 15. 260. 10. 217. 17. 2086800700042 237. 9. 1. 2086800700043 258. 16. 234. 11. 227. 17. 2086800700044 226. 9. 2. 2086800700045 ENDDATA 8 0 2086800700046 ENDSUBENT 45 0 2086800799999 SUBENT 20868008 20150721 22432086800800001 BIB 7 18 2086800800002 REACTION (49-IN-115(N,INL)49-IN-115-M,,SIG,,FIS) 2086800800003 INC-SOURCE Mock-Fission (Po-210+Be+B+F) neutron sources. 2086800800004 Mock-Fission source in stainless steel container; 2086800800005 17.0 x 15.0 mm (h x diam.); amount of radioactive 2086800800006 material - 1Ci. 2086800800007 Mock-Fission neutron source is a mixture of Po, Be, B, 2086800800008 F (and Li) in the correct proportions constitutes a 2086800800009 neutron source, the spectrum of which resembles an 2086800800010 uranium fission spectrum. 2086800800011 DECAY-DATA (49-IN-115-M,4.50HR,DG,335.,0.500) 2086800800012 SAMPLE .Natural indium sphere 1 cm in diameter. 2086800800013 FLAG (1.) detector without surrounding by B-10 sphere 2086800800014 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086800800015 STATUS (TABLE) .Decay data taken from text, cross section 2086800800016 data from table VI.1 of INDC-430,1970 2086800800017 HISTORY (20120719A) SD: 49-IN-116-M -> 49-IN-116-M1+M2 in 2086800800018 REACTION code and DECAY-DATA. Description of FLAG was 2086800800019 changed. Part of data were moved to Subent 030. 2086800800020 ENDBIB 18 0 2086800800021 COMMON 1 3 2086800800022 EN-DUMMY 2086800800023 MEV 2086800800024 1.5 2086800800025 ENDCOMMON 3 0 2086800800026 DATA 3 2 2086800800027 DATA DATA-ERR FLAG 2086800800028 MB MB NO-DIM 2086800800029 229.0 28.0 2. 2086800800030 252.0 19.0 1. 2086800800031 ENDDATA 4 0 2086800800032 ENDSUBENT 31 0 2086800899999 SUBENT 20868009 20150721 22432086800900001 BIB 7 15 2086800900002 REACTION (49-IN-115(N,INL)49-IN-115-M,,SIG,,SPA) 2086800900003 INC-SOURCE Am-241+Al in Al-container neutron source. 2086800900004 Am-241+Al neutron source in aluminium container; 2086800900005 72.0 x 12.0 mm (h x diam.); amount of radioactive 2086800900006 material - 5Ci; neutron emission rate 2086800900007 4.4 x 10**4 n/sec; anisotropy factor 1.042. 2086800900008 The source consists of a homogeneous mixture of A1 2086800900009 and 241AmO(2). 2086800900010 SAMPLE .Natural indium sphere 1 cm in diameter. 2086800900011 DECAY-DATA (49-IN-115-M,4.50HR,DG,335.,0.500) 2086800900012 FLAG (1.) detector without surrounding by B-10 sphere 2086800900013 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086800900014 STATUS (TABLE) .Decay data taken from text, cross section 2086800900015 data from table VI.1 of INDC-430,1970 2086800900016 HISTORY (20120719A) SD: Description of FLAG was changed. 2086800900017 ENDBIB 15 0 2086800900018 COMMON 1 3 2086800900019 EN-DUMMY 2086800900020 KEV 2086800900021 500. 2086800900022 ENDCOMMON 3 0 2086800900023 DATA 3 2 2086800900024 DATA DATA-ERR FLAG 2086800900025 MB MB NO-DIM 2086800900026 111. 13. 2. 2086800900027 118. 7. 1. 2086800900028 ENDDATA 4 0 2086800900029 ENDSUBENT 28 0 2086800999999 SUBENT 20868010 20150721 22432086801000001 BIB 7 28 2086801000002 REACTION 1(79-AU-197(N,G)79-AU-198,,SIG,,SPA) 2086801000003 2(79-AU-197(N,G)79-AU-198,,SIG,,SPA) 2086801000004 3(79-AU-197(N,G)79-AU-198,,SIG,,SPA) 2086801000005 4(79-AU-197(N,G)79-AU-198,,SIG,,SPA) 2086801000006 INC-SOURCE1(AM-BE) Am-241+Be, pelleted mixture of Am-oxide + Be in2086801000007 stainless steel container; 48.5 x 22.4 mm (h x diam.); 2086801000008 amount of radioactive material - 3Ci; neutron emission 2086801000009 rate 8.6 x 10**6 n/sec; anisotropy factor 1.039. 2086801000010 2(PU-BE) Pu-239+Be, alloy of Pu + Be in tantalum or 2086801000011 stainless steel container; 52.3 x 39.5 mm (h x diam.); 2086801000012 amount of radioactive material - 5Ci; neutron emission2086801000013 rate 1.0 x 10**7n/sec; anisotropy factor 1.052. 2086801000014 3(RA-BE) Ra-226+Be, pressed mechanical mixture of Ra+Be 2086801000015 in monel or platinum container; 15.4x15.0mm(h x diam.);2086801000016 amount of radioactive material - 0.1Ci; neutron 2086801000017 emission rate 1.5x10**6 n/sec;anisotropy factor 1.014.2086801000018 4(CM-BE) Cm-242+Be, pelleted mixture of Cm-oxide + Be in2086801000019 stainless steel container; 19.4 x 17.4 mm (h x diam.); 2086801000020 amount of radioactive material - 1Ci; neutron emission2086801000021 rate 3.5 x 10**6 n/sec; anisotropy factor 1.012. 2086801000022 DECAY-DATA (79-AU-198-G,3880.MIN,DG,412.,0.96) 2086801000023 SAMPLE .Natural gold sphere 1 cm in diameter. 2086801000024 FLAG (1.) detector without surrounding by B-10 sphere 2086801000025 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086801000026 STATUS (TABLE) .Decay data taken from text, cross section 2086801000027 data from table VI.1 of INDC-430,1970 2086801000028 HISTORY (20120719A) SD: Multiple reaction formalism applied. 2086801000029 Description of FLAG was changed. 2086801000030 ENDBIB 28 0 2086801000031 COMMON 1 3 2086801000032 EN-DUMMY 2086801000033 MEV 2086801000034 4.5 2086801000035 ENDCOMMON 3 0 2086801000036 DATA 9 2 2086801000037 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32086801000038 DATA 4DATA-ERR 4FLAG 2086801000039 MB MB MB MB MB MB 2086801000040 MB MB NO-DIM 2086801000041 47.6 1.3 57.4 1.3 69.6 2.42086801000042 58.6 1.5 2. 2086801000043 51.7 1.1 68.3 1.5 85.9 2.82086801000044 70.8 1.7 1. 2086801000045 ENDDATA 8 0 2086801000046 ENDSUBENT 45 0 2086801099999 SUBENT 20868011 20150721 22432086801100001 BIB 7 14 2086801100002 REACTION (79-AU-197(N,G)79-AU-198,,SIG,,FIS) 2086801100003 INC-SOURCE (CF252) Spont. fission neutron source in monel 2086801100004 container; 15.0 x 15.0 mm (h x diam.); amount of 2086801100005 radioactive material - 8.x 10**(-4)Ci; neutron 2086801100006 emission rate 3.5 x 10**6 n/sec; anisotropy 2086801100007 factor 1.019. 2086801100008 DECAY-DATA (79-AU-198-G,3880.MIN,DG,412.,0.96) 2086801100009 SAMPLE .Natural gold sphere 1 cm in diameter. 2086801100010 FLAG (1.) detector without surrounding by B-10 sphere 2086801100011 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086801100012 STATUS (TABLE) .Decay data taken from text, cross section 2086801100013 data from table VI.1 of INDC-430,1970 2086801100014 HISTORY (20120719A) SD: Description of FLAG was changed. 2086801100015 EN-DUMMY -> KT-DUMMY. 2086801100016 ENDBIB 14 0 2086801100017 COMMON 1 3 2086801100018 KT-DUMMY 2086801100019 MEV 2086801100020 1.42 2086801100021 ENDCOMMON 3 0 2086801100022 DATA 3 2 2086801100023 DATA DATA-ERR FLAG 2086801100024 MB MB NO-DIM 2086801100025 83.1 2.1 2. 2086801100026 95.5 2.3 1. 2086801100027 ENDDATA 4 0 2086801100028 ENDSUBENT 27 0 2086801199999 SUBENT 20868012 20150721 22432086801200001 BIB 7 17 2086801200002 REACTION 1(79-AU-197(N,G)79-AU-198,,SIG) 2086801200003 2(79-AU-197(N,G)79-AU-198,,SIG) 2086801200004 INC-SOURCE1Sb-124+Be in Al-container; anisotropy factor 1.030. 2086801200005 2Sb-124+Be in Ti-container; anisotropy factor 1.105. 2086801200006 Sb-124+Be neutron source in aluminium or titanium 2086801200007 container; 36.0 x 23.0 mm (h x diam.); amount of 2086801200008 radioactive material - 1Ci; neutron 2086801200009 emission rate 1.0 x 10**6 n/sec; anisotropy 2086801200010 factor 1.030. 2086801200011 DECAY-DATA (79-AU-198-G,3880.MIN,DG,412.,0.96) 2086801200012 SAMPLE .Natural gold sphere 1 cm in diameter. 2086801200013 FLAG (1.) detector without surrounding by B-10 sphere 2086801200014 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086801200015 STATUS (TABLE) .Decay data taken from text, cross section 2086801200016 data from table VI.1 of INDC-430,1970 2086801200017 HISTORY (20120719A) SD: Multiple reaction formalism applied. 2086801200018 Description of FLAG was changed. 2086801200019 ENDBIB 17 0 2086801200020 COMMON 1 3 2086801200021 EN-RSL 2086801200022 KEV 2086801200023 1.0 2086801200024 ENDCOMMON 3 0 2086801200025 DATA 6 4 2086801200026 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2FLAG 2086801200027 KEV MB MB MB MB NO-DIM 2086801200028 21.0 715. 30. 1.2086801200029 21.0 380. 15. 2.2086801200030 22.0 655. 40. 1.2086801200031 22.0 380. 25. 2.2086801200032 ENDDATA 6 0 2086801200033 ENDSUBENT 32 0 2086801299999 SUBENT 20868013 20150721 22432086801300001 BIB 7 15 2086801300002 REACTION (79-AU-197(N,G)79-AU-198,,SIG,,SPA) 2086801300003 INC-SOURCE Am-241+Al in Al-container neutron source. 2086801300004 Am-241+Al neutron source in aluminium container; 2086801300005 72.0 x 12.0 mm (h x diam.); amount of radioactive 2086801300006 material - 5Ci; neutron emission rate 2086801300007 4.4 x 10**4 n/sec; anisotropy factor 1.042. 2086801300008 The source consists of a homogeneous mixture of A1 2086801300009 and 241AmO(2). 2086801300010 DECAY-DATA (79-AU-198-G,3880.MIN,DG,412.,0.96) 2086801300011 SAMPLE .Natural gold sphere 1 cm in diameter. 2086801300012 FLAG (1.) detector without surrounding by B-10 sphere 2086801300013 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086801300014 STATUS (TABLE) .Decay data taken from text, cross section 2086801300015 data from table VI.1 of INDC-430,1970 2086801300016 HISTORY (20120719U) SD: Description of FLAG was changed. 2086801300017 ENDBIB 15 0 2086801300018 COMMON 1 3 2086801300019 EN-DUMMY 2086801300020 KEV 2086801300021 500. 2086801300022 ENDCOMMON 3 0 2086801300023 DATA 3 2 2086801300024 DATA DATA-ERR FLAG 2086801300025 MB MB NO-DIM 2086801300026 91. 12. 2. 2086801300027 116. 8. 1. 2086801300028 ENDDATA 4 0 2086801300029 ENDSUBENT 28 0 2086801399999 SUBENT 20868014 20150721 22432086801400001 BIB 7 15 2086801400002 REACTION (79-AU-197(N,G)79-AU-198,,SIG,,SPA) 2086801400003 INC-SOURCE .One Am-241+Li in Li-container neutron source. 2086801400004 Am-241+Li neutron source in stainless steel container; 2086801400005 31.0 x 22.4 mm (h x diam.); amount of radioactive 2086801400006 material - 1.5Ci; neutron emission rate 2086801400007 6.7 x 10**4 n/sec; anisotropy factor 1.023. 2086801400008 AmLi neutron source consists of an intimate 2086801400009 mixture of Li and 241AmO(2). 2086801400010 DECAY-DATA (79-AU-198-G,3880.MIN,DG,412.,0.96) 2086801400011 SAMPLE .Natural gold sphere 1 cm in diameter. 2086801400012 FLAG (1.) detector without surrounding by B-10 sphere 2086801400013 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086801400014 STATUS (TABLE) .Decay data taken from text, cross section 2086801400015 data from table VI.1 of INDC-430,1970 2086801400016 HISTORY (20120719U) SD: Description of FLAG was changed. 2086801400017 ENDBIB 15 0 2086801400018 COMMON 1 3 2086801400019 EN-DUMMY 2086801400020 KEV 2086801400021 100. 2086801400022 ENDCOMMON 3 0 2086801400023 DATA 3 2 2086801400024 DATA DATA-ERR FLAG 2086801400025 MB MB NO-DIM 2086801400026 166.5 4.6 2. 2086801400027 237.8 7.0 1. 2086801400028 ENDDATA 4 0 2086801400029 ENDSUBENT 28 0 2086801499999 SUBENT 20868015 20150721 22432086801500001 BIB 8 35 2086801500002 REACTION 1(79-AU-197(N,2N)79-AU-196,,SIG,,SPA) 2086801500003 2(79-AU-197(N,2N)79-AU-196,,SIG,,SPA) 2086801500004 3(79-AU-197(N,2N)79-AU-196,,SIG,,SPA) 2086801500005 4(79-AU-197(N,2N)79-AU-196,,SIG,,SPA) 2086801500006 INC-SOURCE1(AM-BE) Am-241+Be, pelleted mixture of Am-oxide + Be in2086801500007 stainless steel container; 48.5 x 22.4 mm (h x diam.); 2086801500008 amount of radioactive material - 3Ci; neutron emission 2086801500009 rate 8.6 x 10**6 n/sec; anisotropy factor 1.039. 2086801500010 2(PU-BE) Pu-239+Be, alloy of Pu + Be in tantalum or 2086801500011 stainless steel container; 52.3 x 39.5 mm (h x diam.); 2086801500012 amount of radioactive material - 5Ci; neutron emission2086801500013 rate 1.0 x 10**7n/sec; anisotropy factor 1.052. 2086801500014 3(RA-BE) Ra-226+Be, pressed mechanical mixture of Ra+Be 2086801500015 in monel or platinum container; 15.4x15.0mm(h x diam.);2086801500016 amount of radioactive material - 0.1Ci; neutron 2086801500017 emission rate 1.5x10**6 n/sec;anisotropy factor 1.014.2086801500018 4(CM-BE) Cm-242+Be, pelleted mixture of Cm-oxide + Be in2086801500019 stainless steel container; 19.4 x 17.4 mm (h x diam.); 2086801500020 amount of radioactive material - 1Ci; neutron emission2086801500021 rate 3.5 x 10**6 n/sec; anisotropy factor 1.012. 2086801500022 DECAY-DATA (79-AU-196-G,8900.MIN,DG,333.,0.248,DG,356.,0.679, 2086801500023 DG,426.,0.071) 2086801500024 .No data given for the 79-Au-196-m nucleus. 2086801500025 SAMPLE .Natural gold sphere 1 cm in diameter. 2086801500026 FLAG (1.) detector without surrounding by B-10 sphere 2086801500027 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086801500028 REL-REF (R,,J.F.W.Jansen+,J,NP/A,94,235,1967) - Decay data 2086801500029 taken from text of INDC-430,1970 and reference 2086801500030 Nucl.Phys.A94(1967)235 2086801500031 STATUS (TABLE) .cross section data from table VI.1 2086801500032 of INDC-430,1970 2086801500033 HISTORY (20120719A) SD: REL-REF was added. Sum of reactions 2086801500034 changed to one in REACTION code. 2086801500035 (20120719A) SD: Multiple reaction formalism applied. 2086801500036 Description of FLAG was changed. 2086801500037 ENDBIB 35 0 2086801500038 COMMON 1 3 2086801500039 EN-DUMMY 2086801500040 MEV 2086801500041 4.5 2086801500042 ENDCOMMON 3 0 2086801500043 DATA 9 2 2086801500044 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32086801500045 DATA 4DATA-ERR 4FLAG 2086801500046 MB MB MB MB MB MB 2086801500047 MB MB NO-DIM 2086801500048 37.6 0.8 29.6 0.6 40.9 1.22086801500049 40.2 1.0 1. 2086801500050 30.8 0.7 24.9 0.6 35.0 1.42086801500051 35.1 1.0 2. 2086801500052 ENDDATA 8 0 2086801500053 ENDSUBENT 52 0 2086801599999 SUBENT 20868016 20150721 22432086801600001 BIB 8 20 2086801600002 REACTION (79-AU-197(N,2N)79-AU-196,,SIG,,FIS) 2086801600003 INC-SOURCE (CF252) Spont. fission neutron source in monel 2086801600004 container; 15.0 x 15.0 mm (h x diam.); amount of 2086801600005 radioactive material - 8.x 10**(-4)Ci; neutron 2086801600006 emission rate 3.5 x 10**6 n/sec; anisotropy 2086801600007 factor 1.019. 2086801600008 DECAY-DATA (79-AU-196-G,8900.MIN,DG,333.,0.248,DG,356.,0.679, 2086801600009 DG,426.,0.071) 2086801600010 .No data given for the 79-Au-196-m nucleus. 2086801600011 SAMPLE .Natural gold sphere 1 cm in diameter. 2086801600012 FLAG (1.) detector without surrounding by B-10 sphere 2086801600013 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086801600014 REL-REF (R,,J.F.W.Jansen+,J,NP/A,94,235,1967) - Decay data 2086801600015 taken from text of INDC-430,1970 and reference 2086801600016 Nucl.Phys.A94(1967)235 2086801600017 STATUS (TABLE) Data from table VI.1 of INDC-430,1970. 2086801600018 HISTORY (20120719A) SD: REL-REF was added. Sum of reactions 2086801600019 changed to one in REACTION code. 2086801600020 (20120719A) SD: Description of FLAG was changed. 2086801600021 EN-DUMMY -> KT-DUMMY 2086801600022 ENDBIB 20 0 2086801600023 COMMON 1 3 2086801600024 KT-DUMMY 2086801600025 MEV 2086801600026 1.42 2086801600027 ENDCOMMON 3 0 2086801600028 DATA 3 2 2086801600029 DATA DATA-ERR FLAG 2086801600030 MB MB NO-DIM 2086801600031 4.56 0.14 2. 2086801600032 4.93 0.14 1. 2086801600033 ENDDATA 4 0 2086801600034 ENDSUBENT 33 0 2086801699999 SUBENT 20868017 20150721 22432086801700001 BIB 5 27 2086801700002 REACTION 1(94-PU-239(N,F),,SIG,,SPA) 2086801700003 2(94-PU-239(N,F),,SIG,,SPA) 2086801700004 3(94-PU-239(N,F),,SIG,,SPA) 2086801700005 4(94-PU-239(N,F),,SIG,,SPA) 2086801700006 INC-SOURCE1(AM-BE) Am-241+Be, pelleted mixture of Am-oxide + Be in2086801700007 stainless steel container; 48.5 x 22.4 mm (h x diam.); 2086801700008 amount of radioactive material - 3Ci; neutron emission 2086801700009 rate 8.6 x 10**6 n/sec; anisotropy factor 1.039. 2086801700010 2(PU-BE) Pu-239+Be, alloy of Pu + Be in tantalum or 2086801700011 stainless steel container; 52.3 x 39.5 mm (h x diam.); 2086801700012 amount of radioactive material - 5Ci; neutron emission2086801700013 rate 1.0 x 10**7n/sec; anisotropy factor 1.052. 2086801700014 3(RA-BE) Ra-226+Be, pressed mechanical mixture of Ra+Be 2086801700015 in monel or platinum container; 15.4x15.0mm(h x diam.);2086801700016 amount of radioactive material - 0.1Ci; neutron 2086801700017 emission rate 1.5x10**6 n/sec;anisotropy factor 1.014.2086801700018 4(CM-BE) Cm-242+Be, pelleted mixture of Cm-oxide + Be in2086801700019 stainless steel container; 19.4 x 17.4 mm (h x diam.); 2086801700020 amount of radioactive material - 1Ci; neutron emission2086801700021 rate 3.5 x 10**6 n/sec; anisotropy factor 1.012. 2086801700022 SAMPLE .About 0.1 mg/cm2 Pu electroplated onto a 1 mm thick 2086801700023 nickel backing. Isotopic composition, 98.358% Pu-239, 2086801700024 1.613% Pu-240, 0.029% Pu-241 and less 2086801700025 than 0.0005% Pu-242. 2086801700026 STATUS (TABLE) .Data taken from table VI.1 of INDC-430,1970 2086801700027 HISTORY (20120719A) SD: Multiple reaction formalism applied. 2086801700028 FLAG was deleted. 2086801700029 ENDBIB 27 0 2086801700030 COMMON 1 3 2086801700031 EN-DUMMY 2086801700032 MEV 2086801700033 4.5 2086801700034 ENDCOMMON 3 0 2086801700035 DATA 8 1 2086801700036 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32086801700037 DATA 4DATA-ERR 4 2086801700038 MB MB MB MB MB MB 2086801700039 MB MB 2086801700040 1835. 60. 1790. 60. 1750. 60.2086801700041 1820. 60. 2086801700042 ENDDATA 6 0 2086801700043 ENDSUBENT 42 0 2086801799999 SUBENT 20868018 20150721 22432086801800001 BIB 5 12 2086801800002 REACTION (94-PU-239(N,F),,SIG,,FIS) 2086801800003 INC-SOURCE (CF252) Spont. fission neutron source in monel 2086801800004 container; 15.0 x 15.0 mm (h x diam.); amount of 2086801800005 radioactive material - 8.x 10**(-4)Ci; neutron 2086801800006 emission rate 3.5 x 10**6 n/sec; anisotropy 2086801800007 factor 1.019. 2086801800008 SAMPLE .About 0.1 mg/cm2 Pu electroplated onto a 1 mm thick 2086801800009 nickel backing. Isotopic composition, 98.358% Pu-239, 2086801800010 1.613% Pu-240, 0.029% Pu-241 and less 2086801800011 than 0.0005% Pu-242. 2086801800012 STATUS (TABLE) .Data taken from table VI.1 of INDC-430,1970 2086801800013 HISTORY (20120719A) SD: INC-SOURCE update. EN-DUMMY -> KT-DUMMY2086801800014 ENDBIB 12 0 2086801800015 COMMON 1 3 2086801800016 KT-DUMMY 2086801800017 MEV 2086801800018 1.42 2086801800019 ENDCOMMON 3 0 2086801800020 DATA 2 1 2086801800021 DATA DATA-ERR 2086801800022 MB MB 2086801800023 1800. 60. 2086801800024 ENDDATA 3 0 2086801800025 ENDSUBENT 24 0 2086801899999 SUBENT 20868019 20150721 22432086801900001 BIB 5 13 2086801900002 REACTION (94-PU-239(N,F),,SIG) 2086801900003 INC-SOURCE Sb-124+Be in Ti-container; anisotropy factor 1.105. 2086801900004 Sb-124+Be neutron source in aluminium or titanium 2086801900005 container; 36.0 x 23.0 mm (h x diam.); amount of 2086801900006 radioactive material - 1Ci; neutron 2086801900007 emission rate 1.0 x 10**6 n/sec; anisotropy 2086801900008 factor 1.030. 2086801900009 SAMPLE .About 0.1 mg/cm2 Pu electroplated onto a 1 mm thick 2086801900010 nickel backing. Isotopic composition, 98.358% Pu-239, 2086801900011 1.613% Pu-240, 0.029% Pu-241 and less 2086801900012 than 0.0005% Pu-242. 2086801900013 STATUS (TABLE) .Data taken from table VI.1 of INDC-430,1970 2086801900014 HISTORY (20120719U) SD: FLAG was deleted. 2086801900015 ENDBIB 13 0 2086801900016 NOCOMMON 0 0 2086801900017 DATA 4 1 2086801900018 EN EN-RSL DATA DATA-ERR 2086801900019 KEV KEV MB MB 2086801900020 21. 1. 1700. 60. 2086801900021 ENDDATA 3 0 2086801900022 ENDSUBENT 21 0 2086801999999 SUBENT 20868020 20150721 22432086802000001 BIB 5 14 2086802000002 REACTION (94-PU-239(N,F),,SIG,,SPA) 2086802000003 INC-SOURCE Am-241+Al in Al-container neutron source. 2086802000004 Am-241+Al neutron source in aluminium container; 2086802000005 72.0 x 12.0 mm (h x diam.); amount of radioactive 2086802000006 material - 5Ci; neutron emission rate 2086802000007 4.4 x 10**4 n/sec; anisotropy factor 1.042. 2086802000008 The source consists of a homogeneous mixture of A1 2086802000009 and 241AmO(2). 2086802000010 SAMPLE .About 0.1 mg/cm2 Pu electroplated onto a 1 mm thick 2086802000011 nickel backing. Isotopic composition, 98.358% Pu-239, 2086802000012 1.613% Pu-240, 0.029% Pu-241 and less 2086802000013 than 0.0005% Pu-242. 2086802000014 STATUS (TABLE) .Data taken from table VI.1 of INDC-430,1970 2086802000015 HISTORY (20120719U) SD: INC-SOURCE update 2086802000016 ENDBIB 14 0 2086802000017 COMMON 1 3 2086802000018 EN-DUMMY 2086802000019 KEV 2086802000020 500. 2086802000021 ENDCOMMON 3 0 2086802000022 DATA 2 1 2086802000023 DATA DATA-ERR 2086802000024 MB MB 2086802000025 1700. 60. 2086802000026 ENDDATA 3 0 2086802000027 ENDSUBENT 26 0 2086802099999 SUBENT 20868021 20150721 22432086802100001 BIB 5 14 2086802100002 REACTION (94-PU-239(N,F),,SIG,,SPA) 2086802100003 INC-SOURCE .One Am-241+Li in Li-container neutron source. 2086802100004 Am-241+Li neutron source in stainless steel container; 2086802100005 31.0 x 22.4 mm (h x diam.); amount of radioactive 2086802100006 material - 1.5Ci; neutron emission rate 2086802100007 6.7 x 10**4 n/sec; anisotropy factor 1.023. 2086802100008 AmLi neutron source consists of an intimate 2086802100009 mixture of Li and 241AmO(2). 2086802100010 SAMPLE About 0.1 mg/cm2 Pu electroplated onto a 1 mm thick 2086802100011 nickel backing. Isotopic composition, 98.358% Pu-239, 2086802100012 1.613% Pu-240, 0.029% Pu-241 and less 2086802100013 than 0.0005% Pu-242. 2086802100014 STATUS (TABLE) .Data taken from table VI.1 of INDC-430,1970 2086802100015 HISTORY (20120719U) SD: INC-SOURCE update 2086802100016 ENDBIB 14 0 2086802100017 COMMON 1 3 2086802100018 EN-DUMMY 2086802100019 KEV 2086802100020 100. 2086802100021 ENDCOMMON 3 0 2086802100022 DATA 2 1 2086802100023 DATA DATA-ERR 2086802100024 MB MB 2086802100025 1565. 160. 2086802100026 ENDDATA 3 0 2086802100027 ENDSUBENT 26 0 2086802199999 SUBENT 20868022 20150721 22432086802200001 BIB 5 25 2086802200002 REACTION 1(93-NP-237(N,F),,SIG,,SPA) 2086802200003 2(93-NP-237(N,F),,SIG,,SPA) 2086802200004 3(93-NP-237(N,F),,SIG,,SPA) 2086802200005 4(93-NP-237(N,F),,SIG,,SPA) 2086802200006 INC-SOURCE1(AM-BE) Am-241+Be, pelleted mixture of Am-oxide + Be in2086802200007 stainless steel container; 48.5 x 22.4 mm (h x diam.); 2086802200008 amount of radioactive material - 3Ci; neutron emission 2086802200009 rate 8.6 x 10**6 n/sec; anisotropy factor 1.039. 2086802200010 2(PU-BE) Pu-239+Be, alloy of Pu + Be in tantalum or 2086802200011 stainless steel container; 52.3 x 39.5 mm (h x diam.); 2086802200012 amount of radioactive material - 5Ci; neutron emission2086802200013 rate 1.0 x 10**7n/sec; anisotropy factor 1.052. 2086802200014 3(RA-BE) Ra-226+Be, pressed mechanical mixture of Ra+Be 2086802200015 in monel or platinum container; 15.4x15.0mm(h x diam.);2086802200016 amount of radioactive material - 0.1Ci; neutron 2086802200017 emission rate 1.5x10**6 n/sec;anisotropy factor 1.014.2086802200018 4(CM-BE) Cm-242+Be, pelleted mixture of Cm-oxide + Be in2086802200019 stainless steel container; 19.4 x 17.4 mm (h x diam.); 2086802200020 amount of radioactive material - 1Ci; neutron emission2086802200021 rate 3.5 x 10**6 n/sec; anisotropy factor 1.012. 2086802200022 SAMPLE .About 0.1 mg/cm2 Np-237 (enrichment 100%) 2086802200023 electroplated onto a 1 mm thick nickel backing. 2086802200024 STATUS (TABLE) .Data taken from table VI.1 of INDC-430,1970 2086802200025 HISTORY (20120719A) SD: Multiple reaction formalism applied. 2086802200026 FLAG was deleted. 2086802200027 ENDBIB 25 0 2086802200028 COMMON 1 3 2086802200029 EN-DUMMY 2086802200030 MEV 2086802200031 4.5 2086802200032 ENDCOMMON 3 0 2086802200033 DATA 8 1 2086802200034 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32086802200035 DATA 4DATA-ERR 4 2086802200036 MB MB MB MB MB MB 2086802200037 MB MB 2086802200038 1500. 45. 1375. 40. 1275. 50.2086802200039 1500. 60. 2086802200040 ENDDATA 6 0 2086802200041 ENDSUBENT 40 0 2086802299999 SUBENT 20868023 20150721 22432086802300001 BIB 5 10 2086802300002 REACTION (93-NP-237(N,F),,SIG,,FIS) 2086802300003 INC-SOURCE (CF252) Spont. fission neutron source in monel 2086802300004 container; 15.0 x 15.0 mm (h x diam.); amount of 2086802300005 radioactive material - 8.x 10**(-4)Ci; neutron 2086802300006 emission rate 3.5 x 10**6 n/sec; anisotropy 2086802300007 factor 1.019. 2086802300008 SAMPLE .About 0.1 mg/cm2 Np-237 (enrichment 100%) 2086802300009 electroplated onto a 1 mm thick nickel backing. 2086802300010 STATUS (TABLE) .Data taken from table VI.1 of INDC-430,1970 2086802300011 HISTORY (20120719A) SD: INC-SOURCE update. EN-DUMMY -> KT-DUMMY2086802300012 ENDBIB 10 0 2086802300013 COMMON 1 3 2086802300014 KT-DUMMY 2086802300015 MEV 2086802300016 1.42 2086802300017 ENDCOMMON 3 0 2086802300018 DATA 2 1 2086802300019 DATA DATA-ERR 2086802300020 MB MB 2086802300021 1260. 60. 2086802300022 ENDDATA 3 0 2086802300023 ENDSUBENT 22 0 2086802399999 SUBENT 20868024 20150721 22432086802400001 BIB 5 12 2086802400002 REACTION (93-NP-237(N,F),,SIG,,SPA) 2086802400003 INC-SOURCE Am-241+Al in Al-container neutron source. 2086802400004 Am-241+Al neutron source in aluminium container; 2086802400005 72.0 x 12.0 mm (h x diam.); amount of radioactive 2086802400006 material - 5Ci; neutron emission rate 2086802400007 4.4 x 10**4 n/sec; anisotropy factor 1.042. 2086802400008 The source consists of a homogeneous mixture of A1 2086802400009 and 241AmO(2). 2086802400010 SAMPLE .About 0.1 mg/cm2 Np-237 (enrichment 100%) 2086802400011 electroplated onto a 1 mm thick nickel backing. 2086802400012 STATUS (TABLE) .Data taken from table VI.1 of INDC-430,1970 2086802400013 HISTORY (20120719U) SD: INC-SOURCE update 2086802400014 ENDBIB 12 0 2086802400015 COMMON 1 3 2086802400016 EN-DUMMY 2086802400017 KEV 2086802400018 500. 2086802400019 ENDCOMMON 3 0 2086802400020 DATA 2 1 2086802400021 DATA DATA-ERR 2086802400022 MB MB 2086802400023 710. 100. 2086802400024 ENDDATA 3 0 2086802400025 ENDSUBENT 24 0 2086802499999 SUBENT 20868025 20150721 22432086802500001 BIB 5 12 2086802500002 REACTION (93-NP-237(N,F),,SIG,,SPA) 2086802500003 INC-SOURCE .One Am-241+Li in Li-container neutron source. 2086802500004 Am-241+Li neutron source in stainless steel container; 2086802500005 31.0 x 22.4 mm (h x diam.); amount of radioactive 2086802500006 material - 1.5Ci; neutron emission rate 2086802500007 6.7 x 10**4 n/sec; anisotropy factor 1.023. 2086802500008 AmLi neutron source consists of an intimate 2086802500009 mixture of Li and 241AmO(2). 2086802500010 SAMPLE .About 0.1 mg/cm2 Np-237 (enrichment 100%) 2086802500011 electroplated onto a 1 mm thick nickel backing. 2086802500012 STATUS (TABLE) .Data taken from table VI.1 of INDC-430,1970 2086802500013 HISTORY (20120719U) SD: INC-SOURCE update 2086802500014 ENDBIB 12 0 2086802500015 COMMON 1 3 2086802500016 EN-DUMMY 2086802500017 KEV 2086802500018 100. 2086802500019 ENDCOMMON 3 0 2086802500020 DATA 2 1 2086802500021 DATA DATA-ERR 2086802500022 MB MB 2086802500023 400. 45. 2086802500024 ENDDATA 3 0 2086802500025 ENDSUBENT 24 0 2086802599999 SUBENT 20868026 20150721 22432086802600001 BIB 5 25 2086802600002 REACTION 1(92-U-0(N,F),,SIG,,SPA) 2086802600003 2(92-U-0(N,F),,SIG,,SPA) 2086802600004 3(92-U-0(N,F),,SIG,,SPA) 2086802600005 4(92-U-0(N,F),,SIG,,SPA) 2086802600006 SAMPLE .About 0.1 mg/cm2 natural uranium electroplated onto 2086802600007 a 1 mm thick nickel backing. 2086802600008 INC-SOURCE1(AM-BE) Am-241+Be, pelleted mixture of Am-oxide + Be in2086802600009 stainless steel container; 48.5 x 22.4 mm (h x diam.); 2086802600010 amount of radioactive material - 3Ci; neutron emission 2086802600011 rate 8.6 x 10**6 n/sec; anisotropy factor 1.039. 2086802600012 2(PU-BE) Pu-239+Be, alloy of Pu + Be in tantalum or 2086802600013 stainless steel container; 52.3 x 39.5 mm (h x diam.); 2086802600014 amount of radioactive material - 5Ci; neutron emission2086802600015 rate 1.0 x 10**7n/sec; anisotropy factor 1.052. 2086802600016 3(RA-BE) Ra-226+Be, pressed mechanical mixture of Ra+Be 2086802600017 in monel or platinum container; 15.4x15.0mm(h x diam.);2086802600018 amount of radioactive material - 0.1Ci; neutron 2086802600019 emission rate 1.5x10**6 n/sec;anisotropy factor 1.014.2086802600020 4(CM-BE) Cm-242+Be, pelleted mixture of Cm-oxide + Be in2086802600021 stainless steel container; 19.4 x 17.4 mm (h x diam.); 2086802600022 amount of radioactive material - 1Ci; neutron emission2086802600023 rate 3.5 x 10**6 n/sec; anisotropy factor 1.012. 2086802600024 STATUS (TABLE) .Data taken from table VI.1 of INDC-430,1970 2086802600025 HISTORY (20120719A) SD: Multiple reaction formalism applied. 2086802600026 FLAG was deleted. 2086802600027 ENDBIB 25 0 2086802600028 COMMON 1 3 2086802600029 EN-DUMMY 2086802600030 MEV 2086802600031 4.5 2086802600032 ENDCOMMON 3 0 2086802600033 DATA 8 1 2086802600034 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32086802600035 DATA 4DATA-ERR 4 2086802600036 MB MB MB MB MB MB 2086802600037 MB MB 2086802600038 490. 20. 455. 15. 365. 20.2086802600039 495. 25. 2086802600040 ENDDATA 6 0 2086802600041 ENDSUBENT 40 0 2086802699999 SUBENT 20868027 20150721 22432086802700001 BIB 5 10 2086802700002 REACTION (92-U-0(N,F),,SIG,,FIS) 2086802700003 SAMPLE .About 0.1 mg/cm2 natural uranium electroplated onto 2086802700004 a 1 mm thick nickel backing. 2086802700005 INC-SOURCE (CF252) Spont. fission neutron source in monel 2086802700006 container; 15.0 x 15.0 mm (h x diam.); amount of 2086802700007 radioactive material - 8.x 10**(-4)Ci; neutron 2086802700008 emission rate 3.5 x 10**6 n/sec; anisotropy 2086802700009 factor 1.019. 2086802700010 STATUS (TABLE) .Data taken from table VI.1 of INDC-430,1970 2086802700011 HISTORY (20120719A) SD: INC-SOURCE update. EN-DUMMY -> KT-DUMMY2086802700012 ENDBIB 10 0 2086802700013 COMMON 1 3 2086802700014 KT-DUMMY 2086802700015 MEV 2086802700016 1.42 2086802700017 ENDCOMMON 3 0 2086802700018 DATA 2 1 2086802700019 DATA DATA-ERR 2086802700020 MB MB 2086802700021 310. 25. 2086802700022 ENDDATA 3 0 2086802700023 ENDSUBENT 22 0 2086802799999 SUBENT 20868028 20150721 22432086802800001 BIB 5 12 2086802800002 REACTION (92-U-0(N,F),,SIG,,SPA) 2086802800003 INC-SOURCE Am-241+Al in Al-container neutron source. 2086802800004 Am-241+Al neutron source in aluminium container; 2086802800005 72.0 x 12.0 mm (h x diam.); amount of radioactive 2086802800006 material - 5Ci; neutron emission rate 2086802800007 4.4 x 10**4 n/sec; anisotropy factor 1.042. 2086802800008 The source consists of a homogeneous mixture of A1 2086802800009 and 241AmO(2). 2086802800010 SAMPLE .About 0.1 mg/cm2 natural uranium electroplated onto 2086802800011 a 1 mm thick nickel backing. 2086802800012 STATUS (TABLE) .Data taken from table VI.1 of INDC-430,1970 2086802800013 HISTORY (20120719U) SD: INC-SOURCE update 2086802800014 ENDBIB 12 0 2086802800015 COMMON 1 3 2086802800016 EN-DUMMY 2086802800017 KEV 2086802800018 500. 2086802800019 ENDCOMMON 3 0 2086802800020 DATA 2 1 2086802800021 DATA DATA-ERR 2086802800022 MB MB 2086802800023 200. 40. 2086802800024 ENDDATA 3 0 2086802800025 ENDSUBENT 24 0 2086802899999 SUBENT 20868029 20150721 22432086802900001 BIB 7 14 2086802900002 REACTION (49-IN-115(N,G)49-IN-116-M1+M2,,SIG,,FIS) 2086802900003 INC-SOURCE (CF252) Spont. fission neutron source in monel 2086802900004 container; 15.0 x 15.0 mm (h x diam.); amount of 2086802900005 radioactive material - 8.x 10**(-4)Ci; neutron 2086802900006 emission rate 3.5 x 10**6 n/sec; anisotropy 2086802900007 factor 1.019. 2086802900008 DECAY-DATA (49-IN-116-M1,54.13MIN,DG,1293.,0.837) 2086802900009 SAMPLE .Natural indium sphere 1 cm in diameter. 2086802900010 FLAG (1.) detector without surrounding by B-10 sphere 2086802900011 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086802900012 that useful in the energy region below 1.5 MeV 2086802900013 STATUS (TABLE) .Decay data taken from text, cross section 2086802900014 data from table VI.1 of INDC-430,1970 2086802900015 HISTORY (20120719T) SD: Part of Subent 003 moved to this subent2086802900016 ENDBIB 14 0 2086802900017 COMMON 1 3 2086802900018 KT-DUMMY 2086802900019 MEV 2086802900020 1.42 2086802900021 ENDCOMMON 3 0 2086802900022 DATA 3 2 2086802900023 DATA DATA-ERR FLAG 2086802900024 MB MB NO-DIM 2086802900025 118.9 4.5 2.0 2086802900026 125.3 4.3 1.0 2086802900027 ENDDATA 4 0 2086802900028 ENDSUBENT 27 0 2086802999999 SUBENT 20868030 20150721 22432086803000001 BIB 7 13 2086803000002 REACTION (49-IN-115(N,INL)49-IN-115-M,,SIG,,FIS) 2086803000003 INC-SOURCE (CF252) Spont. fission neutron source in monel 2086803000004 container; 15.0 x 15.0 mm (h x diam.); amount of 2086803000005 radioactive material - 8.x 10**(-4)Ci; neutron 2086803000006 emission rate 3.5 x 10**6 n/sec; anisotropy 2086803000007 factor 1.019. 2086803000008 DECAY-DATA (49-IN-115-M,4.50HR,DG,335.,0.500) 2086803000009 SAMPLE .Natural indium sphere 1 cm in diameter. 2086803000010 FLAG (1.) detector without surrounding by B-10 sphere 2086803000011 (2.) detector with surrounding by 2.2 g/cm2 B-10 sphere2086803000012 STATUS (TABLE) .Decay data taken from text, cross section 2086803000013 data from table VI.1 of INDC-430,1970 2086803000014 HISTORY (20120719T) SD: Part of Subent 008 moved to this subent2086803000015 ENDBIB 13 0 2086803000016 COMMON 1 3 2086803000017 KT-DUMMY 2086803000018 MEV 2086803000019 1.42 2086803000020 ENDCOMMON 3 0 2086803000021 DATA 3 2 2086803000022 DATA DATA-ERR FLAG 2086803000023 MB MB NO-DIM 2086803000024 175. 7. 2. 2086803000025 188. 8. 1. 2086803000026 ENDDATA 4 0 2086803000027 ENDSUBENT 26 0 2086803099999 ENDENTRY 30 0 2086899999999