ENTRY 23408 20180918 22712340800000001 SUBENT 23408001 20180918 22712340800100001 BIB 9 15 2340800100002 TITLE The mass yield curve for fission of Am-241 by pile 2340800100003 neutrons 2340800100004 AUTHOR (J.G.Cuninghame) 2340800100005 INSTITUTE (2UK HAR) 2340800100006 REFERENCE (J,JIN,4,1,1957) 2340800100007 FACILITY (REAC,2UK HAR) 2340800100008 (OSCIP) 2340800100009 INC-SOURCE (REAC) Flux of 10**12 n/cm2s 2340800100010 INC-SPECT The neutron flux is approximately 85% thermal with 2340800100011 Maxwellian distribution up to 0.3 eV and 15% fast 2340800100012 neutrons above 0.3 eV. The ratio of neutrons of 2340800100013 energies >1MeV to those of energies <1MeV 1:75. 2340800100014 SAMPLE 0.1 to 1 mg Am-241 purely separated from plutonium 2340800100015 dissolved in 0.5 N nitric acid. 2340800100016 HISTORY (20180918C) VS 2340800100017 ENDBIB 15 0 2340800100018 COMMON 1 3 2340800100019 EN-DUMMY 2340800100020 EV 2340800100021 0.0253 2340800100022 ENDCOMMON 3 0 2340800100023 ENDSUBENT 22 0 2340800199999 SUBENT 23408002 20180918 22712340800200001 BIB 5 8 2340800200002 REACTION (95-AM-241(N,F)ELEM/MASS,CUM,FY,,MXW) 2340800200003 ERR-ANALYS (DATA-ERR) The standard deviation determined by root 2340800200004 mean square deviation of all contributing 2340800200005 uncertainties. 2340800200006 DECAY-DATA (48-CD-115-G,54.HR) 2340800200007 (48-CD-115-M,43.D) 2340800200008 ASSUMED (ASSUM,95-AM-241(N,F)48-CD-115-M,CUM,FY,,MXW) estimated2340800200009 STATUS (TABLE) Table 1 of J.Inorg.Nucl.Chem.4(1957)1 2340800200010 ENDBIB 8 0 2340800200011 COMMON 1 3 2340800200012 ASSUM 2340800200013 PC/FIS 2340800200014 0.004 2340800200015 ENDCOMMON 3 0 2340800200016 DATA 5 19 2340800200017 ELEMENT MASS ISOMER DATA DATA-ERR 2340800200018 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS 2340800200019 38. 89. 0.81 0.05 2340800200020 39. 91. 1.16 0.08 2340800200021 40. 95. 3.90 0.51 2340800200022 40. 97. 3.55 0.46 2340800200023 42. 99. 6.85 0.41 2340800200024 47. 111. 0.89 0.05 2340800200025 47. 113. 0.18 0.01 2340800200026 48. 115. 0. 0.046 0.003 2340800200027 48. 115. 0.050 0.004 2340800200028 50. 121. 0.045 0.006 2340800200029 51. 131. 3.71 0.19 2340800200030 52. 132. 4.48 0.31 2340800200031 55. 137. 9.20 1.84 2340800200032 56. 139. 6.22 0.31 2340800200033 56. 140. 6.0 0.36 2340800200034 58. 141. 5.04 0.66 2340800200035 58. 144. 3.15 0.41 2340800200036 59. 143. 3.32 0.36 2340800200037 60. 147. 2.06 0.33 2340800200038 ENDDATA 21 0 2340800200039 ENDSUBENT 38 0 2340800299999 SUBENT 23408003 20180919 22712340800300001 BIB 3 5 2340800300002 REACTION (95-AM-241(N,F)55-CS-136,IND,FY,,MXW) 2340800300003 ERR-ANALYS (DATA-ERR) The standard deviation determined by root 2340800300004 mean square deviation of all contributing 2340800300005 uncertainties. 2340800300006 STATUS (TABLE) Table 1 of J.Inorg.Nucl.Chem.4(1957)1 2340800300007 ENDBIB 5 0 2340800300008 NOCOMMON 0 0 2340800300009 DATA 2 1 2340800300010 DATA DATA-ERR 2340800300011 PC/FIS PC/FIS 2340800300012 0.288 0.032 2340800300013 ENDDATA 3 0 2340800300014 ENDSUBENT 13 0 2340800399999 SUBENT 23408004 20180919 22712340800400001 BIB 4 6 2340800400002 REACTION (95-AM-241(N,F),,NU,,MXW,DERIV) 2340800400003 ANALYSIS From the fit to the experimental data and 2340800400004 normalization to 200% fission products yield the 2340800400005 peak-to-trough ratio of 160 was derived. 2340800400006 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties. 2340800400007 STATUS (TABLE) Text, page 1 of J.Inorg.Nucl.Chem.4(1957)1 2340800400008 ENDBIB 6 0 2340800400009 NOCOMMON 0 0 2340800400010 DATA 2 1 2340800400011 DATA DATA-ERR 2340800400012 PRT/FIS PRT/FIS 2340800400013 3. 0.5 2340800400014 ENDDATA 3 0 2340800400015 ENDSUBENT 14 0 2340800499999 ENDENTRY 4 0 2340899999999