ENTRY 10649 20080817 13501064900000001 SUBENT 10649001 20080817 13501064900100001 BIB 11 20 1064900100002 INSTITUTE (1USAANL) 1064900100003 REFERENCE (J,NSE,64,897,197712) 1064900100004 AUTHOR (D.L.Smith) 1064900100005 TITLE Measurement of Cross Sections for the 1064900100006 23-Na(n,n' gamma) 23-Na reaction near threshold 1064900100007 FACILITY (ACCEL,1USAANL) Fast Neutron Generator 1064900100008 INC-SOURCE (P-LI7) Protons on lithium-7 1064900100009 SAMPLE Metallic sodium samples in stainless steel cans. 1064900100010 DETECTOR (GELI) Germanium-lithium detector 1064900100011 CORRECTION Data corrected for effects of geometry, neutron source 1064900100012 characteristics, absorption and multiple scattering of 1064900100013 neutrons, absorption of gammas, and lithium target 1064900100014 thickness 1064900100015 STATUS (APRVD) Approved by D.Smith, 1977/5/23. 1064900100016 Data taken from private comm., Smith, 1977/2. 1064900100017 HISTORY (19770307C) 1064900100018 (19780222U) BIB update. 1064900100019 (19831109A) BIB update, data headings corrected. 1064900100020 (20080817A) Converted to new date formats, lower case. 1064900100021 BIB update. 1064900100022 ENDBIB 20 0 1064900100023 NOCOMMON 0 0 1064900100024 ENDSUBENT 23 0 1064900199999 SUBENT 10649002 20080817 13501064900200001 BIB 3 17 1064900200002 REACTION 1((11-NA-23(N,INL)11-NA-23,PAR,DA,G,4PI)/ 1064900200003 (92-U-235(N,F),,SIG)) 1064900200004 2(11-NA-23(N,INL)11-NA-23,PAR,DA,G,4PI) 1064900200005 MONITOR 2(92-U-235(N,F),,SIG) ENDF/B-IV fission cross sections 1064900200006 Uranium in fission detector enriched to 93.3% 235U. 1064900200007 ERR-ANALYS1(DATA-ERR) Overall ratio error is estimated to be 8% 1064900200008 due to contributions from the following sources: 1064900200009 - detector counting efficiency (5%), 1064900200010 - geometric effects (3%), 1064900200011 - neutron source characteristics (>2%), 1064900200012 - gamma detector efficiency (4%), 1064900200013 - mass of uranium deposit (1%), 1064900200014 - gamma absorption in sample (1%), 1064900200015 - neutron absorption in sample (2%), 1064900200016 - neutron multiple scattering (2.4%). 1064900200017 2(DATA-ERR) Relative uncertainties combined with 1064900200018 normalization error. 1064900200019 ENDBIB 17 0 1064900200020 COMMON 2 3 1064900200021 E ANG 1064900200022 MEV ADEG 1064900200023 0.438 55. 1064900200024 ENDCOMMON 3 0 1064900200025 DATA 6 37 1064900200026 EN EN-RSL DATA 1DATA-ERR 1DATA 2DATA-ERR 21064900200027 MEV MEV NO-DIM NO-DIM MB MB 1064900200028 0.5 0.08 0.00571 0.00046 6.7 0.6 1064900200029 0.54 0.08 0.00817 0.00065 9.5 0.9 1064900200030 0.54 0.08 0.00647 0.00052 7.5 0.7 1064900200031 0.54 0.08 0.00802 0.00064 9.3 0.8 1064900200032 0.59 0.08 0.0616 0.0049 71.2 6.4 1064900200033 0.64 0.08 0.106 0.008 122.0 11.0 1064900200034 0.68 0.08 0.175 0.014 201.0 18.0 1064900200035 0.73 0.07 0.297 0.024 337.0 30.0 1064900200036 0.79 0.07 0.339 0.027 382.0 34.0 1064900200037 0.83 0.07 0.279 0.022 317.0 29.0 1064900200038 0.88 0.07 0.22 0.018 256.0 23.0 1064900200039 0.93 0.07 0.212 0.017 251.0 23.0 1064900200040 0.99 0.07 0.277 0.022 333.0 30.0 1064900200041 1.03 0.07 0.425 0.034 518.0 47.0 1064900200042 1.03 0.07 0.398 0.032 486.0 44.0 1064900200043 1.08 0.07 0.432 0.035 536.0 48.0 1064900200044 1.13 0.07 0.367 0.029 459.0 41.0 1064900200045 1.18 0.07 0.399 0.032 500.0 45.0 1064900200046 1.23 0.07 0.544 0.044 682.0 61.0 1064900200047 1.27 0.07 0.36 0.029 451.0 41.0 1064900200048 1.33 0.07 0.239 0.019 300.0 27.0 1064900200049 1.38 0.06 0.197 0.016 247.0 22.0 1064900200050 1.43 0.06 0.263 0.021 331.0 30.0 1064900200051 1.48 0.06 0.273 0.022 344.0 31.0 1064900200052 1.54 0.06 0.222 0.018 279.0 25.0 1064900200053 1.54 0.06 0.206 0.016 260.0 23.0 1064900200054 1.59 0.06 0.283 0.023 357.0 32.0 1064900200055 1.64 0.06 0.379 0.03 478.0 43.0 1064900200056 1.68 0.06 0.327 0.026 413.0 37.0 1064900200057 1.73 0.06 0.452 0.036 571.0 51.0 1064900200058 1.78 0.06 0.475 0.038 601.0 54.0 1064900200059 1.83 0.06 0.384 0.031 487.0 44.0 1064900200060 1.89 0.06 0.31 0.025 393.0 35.0 1064900200061 1.94 0.06 0.422 0.034 536.0 48.0 1064900200062 1.99 0.06 0.485 0.039 617.0 56.0 1064900200063 2.04 0.06 0.365 0.029 464.0 42.0 1064900200064 2.04 0.06 0.403 0.032 513.0 46.0 1064900200065 ENDDATA 39 0 1064900200066 ENDSUBENT 65 0 1064900299999 SUBENT 10649003 20080817 13501064900300001 BIB 3 3 1064900300002 REACTION (11-NA-23(N,INL)11-NA-23,PAR,DA,G,RSD) 1064900300003 MONITOR Plastic scintillator used as flux monitor. 1064900300004 ERR-ANALYS (DATA-ERR) Relative uncertainty of gamma yields. 1064900300005 ENDBIB 3 0 1064900300006 COMMON 2 3 1064900300007 E DATA-ERR 1064900300008 MEV PER-CENT 1064900300009 0.438 5.0 1064900300010 ENDCOMMON 3 0 1064900300011 DATA 3 81 1064900300012 EN COS DATA 1064900300013 MEV NO-DIM NO-DIM 1064900300014 0.644 0.865 1.055 1064900300015 0.644 0.646 1.002 1064900300016 0.644 0.505 0.970 1064900300017 0.644 0.348 0.967 1064900300018 0.644 0.181 0.959 1064900300019 0.644 0.008 1.003 1064900300020 0.644 -0.165 1.005 1064900300021 0.644 -0.334 0.997 1064900300022 0.644 -0.492 1.021 1064900300023 0.644 -0.636 1.015 1064900300024 0.644 -0.701 1.022 1064900300025 0.793 0.865 1.000 1064900300026 0.793 0.767 0.994 1064900300027 0.793 0.646 0.968 1064900300028 0.793 0.505 1.001 1064900300029 0.793 0.349 1.018 1064900300030 0.793 0.181 0.972 1064900300031 0.793 0.009 0.993 1064900300032 0.793 -0.165 1.012 1064900300033 0.793 -0.334 1.017 1064900300034 0.793 -0.492 1.022 1064900300035 0.793 -0.636 1.035 1064900300036 0.793 -0.701 0.978 1064900300037 1.093 0.865 1.020 1064900300038 1.093 0.767 0.970 1064900300039 1.093 0.645 1.028 1064900300040 1.093 0.505 0.979 1064900300041 1.093 0.348 1.003 1064900300042 1.093 0.181 0.984 1064900300043 1.093 0.008 0.998 1064900300044 1.093 -0.165 0.998 1064900300045 1.093 -0.334 0.984 1064900300046 1.093 -0.492 0.975 1064900300047 1.093 -0.636 1.040 1064900300048 1.093 -0.701 1.036 1064900300049 1.245 0.865 1.002 1064900300050 1.245 0.767 0.974 1064900300051 1.245 0.645 0.982 1064900300052 1.245 0.505 1.032 1064900300053 1.245 0.348 1.010 1064900300054 1.245 0.181 0.994 1064900300055 1.245 0.008 0.987 1064900300056 1.245 -0.165 0.991 1064900300057 1.245 -0.334 1.007 1064900300058 1.245 -0.492 0.993 1064900300059 1.245 -0.636 1.029 1064900300060 1.245 -0.701 1.005 1064900300061 1.499 0.865 0.977 1064900300062 1.499 0.766 0.972 1064900300063 1.499 0.645 1.002 1064900300064 1.499 0.504 0.989 1064900300065 1.499 0.348 0.950 1064900300066 1.499 0.181 1.024 1064900300067 1.499 0.008 1.041 1064900300068 1.499 -0.165 1.013 1064900300069 1.499 -0.334 0.982 1064900300070 1.499 -0.492 1.014 1064900300071 1.499 -0.636 1.015 1064900300072 1.499 -0.701 1.038 1064900300073 1.799 0.865 0.949 1064900300074 1.799 0.767 0.926 1064900300075 1.799 0.645 0.988 1064900300076 1.799 0.504 0.995 1064900300077 1.799 0.348 0.999 1064900300078 1.799 0.008 1.048 1064900300079 1.799 -0.165 1.031 1064900300080 1.799 -0.334 1.040 1064900300081 1.799 -0.492 1.032 1064900300082 1.799 -0.636 1.005 1064900300083 1.799 -0.701 1.018 1064900300084 2.044 0.865 0.999 1064900300085 2.044 0.767 1.007 1064900300086 2.044 0.645 1.037 1064900300087 2.044 0.504 1.032 1064900300088 2.044 0.348 1.004 1064900300089 2.044 0.181 0.972 1064900300090 2.044 0.008 0.996 1064900300091 2.044 -0.165 0.990 1064900300092 2.044 -0.334 1.000 1064900300093 2.044 -0.636 0.979 1064900300094 2.044 -0.701 0.992 1064900300095 ENDDATA 83 0 1064900300096 ENDSUBENT 95 0 1064900399999 ENDENTRY 3 0 1064999999999