ENTRY 13883 20031104 00001388300000001 SUBENT 13883001 20031104 00001388300100001 BIB 8 12 1388300100002 INSTITUTE (1USALRL) 1388300100003 REFERENCE (J,RCA,90,833,2002) 1388300100004 AUTHOR (R.W.Lougheed,W.Webster,M.N.Namboodiri,D.R.Nethaway, 1388300100005 K.J.Moody,J.H.Landrum,R.W.Hoff,R.J.Dupzyk,J.H.McQuaid, 1388300100006 R.Gunnink,E.D.Watkins) 1388300100007 TITLE 239Pu and 241Am(n,2n) cross-section measurements near 1388300100008 E(n) = 14 MeV 1388300100009 FACILITY (ICTR,1USALRL) 1388300100010 INC-SOURCE (D-T) 1388300100011 STATUS Data taken from table in reference. 1388300100012 No reply from R.W.Lougheed to author proof. 1388300100013 HISTORY (20030910C) 1388300100014 ENDBIB 12 0 1388300100015 NOCOMMON 0 0 1388300100016 ENDSUBENT 15 0 1388300199999 SUBENT 13883002 20030911 00001388300200001 BIB 8 19 1388300200002 REACTION (94-PU-239(N,2N)94-PU-238,,SIG) 1388300200003 SAMPLE High purity mass-separated 239Pu sample with 1388300200004 238Pu/239Pu ratio of about 6E-10. 1388300200005 METHOD (CHSEP) Irradiated samples dissolved and ion-exchange 1388300200006 spearations performed using Dowex anion-exchange 1388300200007 resin to remove any excess mass. Resulting Pu 1388300200008 fractions electroplated onto Pt disks, which were 1388300200009 heated to fix deposits. 1388300200010 (ACTIV) Counts performed for 1 year after irradiation. 1388300200011 MONITOR (79-AU-197(N,2N)79-AU-196,,SIG) Flux monitor. 1388300200012 Neutron energy determined using 54Fe(n,p) reaction. 1388300200013 DECAY-DATA (94-PU-238,87.75YR,A,5500.) 1388300200014 (94-PU-239,2.41E+4YR) 1388300200015 CORRECTION Data corrected for pileup in alpha spectrum and 1388300200016 for background. 1388300200017 ERR-ANALYS (DATA-ERR) Uncertainties given include counting errors 1388300200018 from determining 238Pu/239Pu ratios, and neutron 1388300200019 fluence errors. 1388300200020 EXP-YEAR (1978) Irradiations in 1977 and 1978. 1388300200021 ENDBIB 19 0 1388300200022 NOCOMMON 0 0 1388300200023 DATA 4 3 1388300200024 EN DATA DATA-ERR MONIT 1388300200025 MEV MB PER-CENT MB 1388300200026 13.8 228. 2.8 2112. 1388300200027 14.0 219. 3.6 2112. 1388300200028 14.8 214. 1.4 2136. 1388300200029 ENDDATA 5 0 1388300200030 ENDSUBENT 29 0 1388300299999 SUBENT 13883003 20030911 00001388300300001 BIB 9 16 1388300300002 REACTION (95-AM-241(N,2N)95-AM-240,,SIG) 1388300300003 SAMPLE High purity AmO2 sample, 99.95% 241Am, in quartz tubes.1388300300004 238Pu/239Pu ratio of about 6E-10. 1388300300005 METHOD (ACTIV) Data irradiated for 15 hrs. Counts done 1388300300006 starting 2 days and continued until 30-40 days after 1388300300007 irradiation. 1388300300008 DETECTOR (GELI) 1388300300009 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) Flux monitor. 1388300300010 Neutron energy determined using Ni foils. 1388300300011 DECAY-DATA (95-AM-240,50.8HR,DG,988.) 1388300300012 (95-AM-241,432.7YR,DG,662.,, DG,722.) 1388300300013 CORRECTION Corrected for decay during irradiation. 1388300300014 ERR-ANALYS (DATA-ERR) Uncertainties given include counting errors 1388300300015 from determining 220Am/241Am ratios, and neutron 1388300300016 fluence errors. 1388300300017 EXP-YEAR (1973) 1388300300018 ENDBIB 16 0 1388300300019 NOCOMMON 0 0 1388300300020 DATA 4 5 1388300300021 EN DATA DATA-ERR MONIT 1388300300022 MEV MB PER-CENT MB 1388300300023 13.67 260. 1.4 124.5 1388300300024 13.98 259. 1.8 120.9 1388300300025 14.29 251. 1.7 119.1 1388300300026 14.77 233. 1.8 111.4 1388300300027 15.12 222. 1.6 107.6 1388300300028 ENDDATA 7 0 1388300300029 ENDSUBENT 28 0 1388300399999 SUBENT 13883004 20030911 00001388300400001 BIB 9 13 1388300400002 REACTION (95-AM-241(N,F)ELEM/MASS,CUM,SIG) 1388300400003 SAMPLE High purity AmO2 sample, 99.95% 241Am, in quartz tubes.1388300400004 238Pu/239Pu ratio of about 6E-10. 1388300400005 METHOD (ACTIV) Data irradiated for 15 hrs. Counts done at end 1388300400006 of irradiation. 1388300400007 DETECTOR (GELI) 1388300400008 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) Flux monitor. 1388300400009 Neutron energy determined using Ni foils. 1388300400010 DECAY-DATA (95-AM-241,432.7YR,DG,662.,, DG,722.) 1388300400011 CORRECTION Not corrected for any additional production from down- 1388300400012 scattered neutrons. 1388300400013 ERR-ANALYS (ERR-S) Statistical uncertainties given. 1388300400014 EXP-YEAR (1973) 1388300400015 ENDBIB 13 0 1388300400016 NOCOMMON 0 0 1388300400017 DATA 5 72 1388300400018 EN MASS ELEMENT DATA ERR-S 1388300400019 MEV NO-DIM NO-DIM MB PER-CENT 1388300400020 13.7 91. 38. 57.0 1.8 1388300400021 13.7 93. 39. 105.8 15.5 1388300400022 13.7 97. 40. 113.0 1.0 1388300400023 13.7 99. 42. 105.5 15.7 1388300400024 13.7 103. 44. 128.8 6.8 1388300400025 13.7 105. 45. 124.4 5.3 1388300400026 13.7 115. 48. 45.5 14.5 1388300400027 13.7 125. 50. 38.1 31.9 1388300400028 13.7 127. 51. 72.1 10.9 1388300400029 13.7 128. 51. 35.6 1.8 1388300400030 13.7 131. 53. 86.7 4.3 1388300400031 13.7 132. 52. 65.3 3.9 1388300400032 13.7 133. 53. 121.3 2.1 1388300400033 13.7 140. 56. 75.5 2.2 1388300400034 14.0 91. 38. 59.1 4.3 1388300400035 14.0 93. 39. 115.6 45.3 1388300400036 14.0 97. 40. 103.8 1.2 1388300400037 14.0 99. 42. 99.5 16.3 1388300400038 14.0 103. 44. 130.8 4.3 1388300400039 14.0 105. 45. 126.0 4.2 1388300400040 14.0 115. 48. 46.0 9.0 1388300400041 14.0 125. 50. 22.7 21.2 1388300400042 14.0 127. 51. 63.6 7.0 1388300400043 14.0 128. 51. 32.1 7.7 1388300400044 14.0 131. 53. 103.3 2.7 1388300400045 14.0 132. 52. 65.0 2.4 1388300400046 14.0 133. 53. 112.7 1.9 1388300400047 14.0 140. 56. 82.1 1.5 1388300400048 14.0 143. 58. 72.5 14.4 1388300400049 14.3 91. 38. 63.9 9.9 1388300400050 14.3 97. 40. 102.2 1.7 1388300400051 14.3 99. 42. 68.4 23.7 1388300400052 14.3 103. 44. 136.8 6.7 1388300400053 14.3 105. 45. 146.5 7.3 1388300400054 14.3 115. 48. 57.3 14.4 1388300400055 14.3 125. 50. 29.5 30.1 1388300400056 14.3 127. 51. 58.0 5.5 1388300400057 14.3 128. 51. 32.7 38.9 1388300400058 14.3 131. 53. 114.1 4.2 1388300400059 14.3 132. 52. 71.9 1.9 1388300400060 14.3 133. 53. 120.8 3.4 1388300400061 14.3 140. 56. 87.8 2.1 1388300400062 14.3 143. 58. 82.4 11.5 1388300400063 14.8 91. 38. 61.5 5.0 1388300400064 14.8 97. 40. 104.7 1.2 1388300400065 14.8 99. 42. 93.2 15.3 1388300400066 14.8 103. 44. 126.2 4.8 1388300400067 14.8 105. 45. 141.1 5.2 1388300400068 14.8 115. 48. 45.8 7.7 1388300400069 14.8 125. 50. 27.4 22.3 1388300400070 14.8 127. 51. 59.0 3.6 1388300400071 14.8 128. 51. 30.4 6.6 1388300400072 14.8 131. 53. 93.4 4.2 1388300400073 14.8 132. 52. 61.9 1.9 1388300400074 14.8 133. 53. 116.7 2.7 1388300400075 14.8 140. 56. 76.5 1.6 1388300400076 14.8 143. 58. 73.8 8.3 1388300400077 15.1 91. 38. 58.7 2.2 1388300400078 15.1 93. 39. 71.8 16.9 1388300400079 15.1 97. 40. 109.6 0.9 1388300400080 15.1 99. 42. 95.9 12.8 1388300400081 15.1 103. 44. 132.5 4.9 1388300400082 15.1 105. 45. 120.6 4.3 1388300400083 15.1 115. 48. 45.6 6.5 1388300400084 15.1 125. 50. 33.0 13.1 1388300400085 15.1 127. 51. 62.7 2.9 1388300400086 15.1 128. 51. 33.9 2.0 1388300400087 15.1 131. 53. 92.2 2.8 1388300400088 15.1 132. 52. 64.0 1.9 1388300400089 15.1 133. 53. 115.0 1.5 1388300400090 15.1 140. 56. 81.3 1.2 1388300400091 15.1 143. 58. 62.8 11.4 1388300400092 ENDDATA 74 0 1388300400093 ENDSUBENT 92 0 1388300499999 ENDENTRY 4 0 1388399999999