ENTRY 10016 19990617 00001001600000001 SUBENT 10016001 19990617 00001001600100001 BIB 10 17 1001600100002 INSTITUTE (1USALAS) 1001600100003 REFERENCE (J,NP/A,133,108,196908) 1001600100004 AUTHOR (D.M.DRAKE) 1001600100005 TITLE Inelastic neutron scattering and gamma production from 1001600100006 fast-neutron bombardment of 235U. 1001600100007 FACILITY (VDG) 8-MeV Van-de-Graaff with Mobley bunching. 1001600100008 INC-SOURCE (P-T) T(p,n) used for neutron energy 4.0 and 6.0 MeV. 1001600100009 (D-D) D(d,n) used for neutron energy 7.5 MeV. 1001600100010 DETECTOR (NAICR) NaI(Tl) detector surrounded by NaI(Tl) anti- 1001600100011 coincidence annulus and a large collimator shield. 1001600100012 Time-of-flight gating used to reduce background and 1001600100013 pulses caused by scattered neutrons. 1001600100014 ERR-ANALYS No information. 1001600100015 STATUS (APRVD) Approved by author. 1001600100016 HISTORY (19691203C) 1001600100017 (19800813A) Converted to REACTION formalism 1001600100018 (19860825A) BIB update. 1001600100019 ENDBIB 17 0 1001600100020 NOCOMMON 0 0 1001600100021 ENDSUBENT 20 0 1001600199999 SUBENT 10016002 19990617 00001001600200001 BIB 2 2 1001600200002 REACTION (92-U-235(N,X)0-G-0,,DA/DE) 1001600200003 HISTORY (19800313A) Subentries 2 - 5 combined 1001600200004 ENDBIB 2 0 1001600200005 NOCOMMON 0 0 1001600200006 DATA 5 73 1001600200007 EN ANG E-MIN E-MAX DATA 1001600200008 MEV ADEG MEV MEV MB/SR/MEV 1001600200009 4.0 55. 0.25 0.50 977. 1001600200010 4.0 55. 0.50 0.75 952. 1001600200011 4.0 55. 0.75 1.00 578. 1001600200012 4.0 55. 1.00 1.25 392. 1001600200013 4.0 55. 1.25 1.50 305. 1001600200014 4.0 55. 1.50 1.75 238. 1001600200015 4.0 55. 1.75 2.00 192. 1001600200016 4.0 55. 2.00 2.25 148. 1001600200017 4.0 55. 2.25 2.50 110. 1001600200018 4.0 55. 2.50 2.75 72. 1001600200019 4.0 55. 2.75 3.00 47. 1001600200020 4.0 55. 3.00 3.25 32. 1001600200021 4.0 55. 3.25 3.50 24. 1001600200022 4.0 55. 3.50 3.75 14. 1001600200023 4.0 55. 3.75 4.00 10. 1001600200024 4.0 55. 4.00 4.25 10. 1001600200025 4.0 55. 4.25 4.50 8. 1001600200026 4.0 55. 4.50 4.75 5. 1001600200027 6.0 55. 0.25 0.50 1092. 1001600200028 6.0 55. 0.50 0.75 1050. 1001600200029 6.0 55. 0.75 1.00 638. 1001600200030 6.0 55. 1.00 1.25 454. 1001600200031 6.0 55. 1.25 1.50 350. 1001600200032 6.0 55. 1.50 1.75 280. 1001600200033 6.0 55. 1.75 2.00 245. 1001600200034 6.0 55. 2.00 2.25 197. 1001600200035 6.0 55. 2.25 2.50 151. 1001600200036 6.0 55. 2.50 2.75 109. 1001600200037 6.0 55. 2.75 3.00 72. 1001600200038 6.0 55. 3.00 3.25 46. 1001600200039 6.0 55. 3.25 3.50 33. 1001600200040 6.0 55. 3.50 3.75 23. 1001600200041 6.0 55. 3.75 4.00 15. 1001600200042 6.0 55. 4.00 4.25 13. 1001600200043 6.0 55. 4.25 4.50 10. 1001600200044 6.0 55. 4.50 4.75 6. 1001600200045 6.0 90. 0.25 0.50 1103. 1001600200046 6.0 90. 0.50 0.75 1080. 1001600200047 6.0 90. 0.75 1.00 623. 1001600200048 6.0 90. 1.00 1.25 458. 1001600200049 6.0 90. 1.25 1.50 358. 1001600200050 6.0 90. 1.50 1.75 284. 1001600200051 6.0 90. 1.75 2.00 239. 1001600200052 6.0 90. 2.00 2.25 207. 1001600200053 6.0 90. 2.25 2.50 149. 1001600200054 6.0 90. 2.50 2.75 101. 1001600200055 6.0 90. 2.75 3.00 73. 1001600200056 6.0 90. 3.00 3.25 47. 1001600200057 6.0 90. 3.25 3.50 34. 1001600200058 6.0 90. 3.50 3.75 24. 1001600200059 6.0 90. 3.75 4.00 17. 1001600200060 6.0 90. 4.00 4.25 14. 1001600200061 6.0 90. 4.25 4.50 10. 1001600200062 6.0 90. 4.50 4.75 5. 1001600200063 7.5 55. 0.25 0.50 1265. 1001600200064 7.5 55. 0.50 0.75 1200. 1001600200065 7.5 55. 0.75 1.00 716. 1001600200066 7.5 55. 1.00 1.25 448. 1001600200067 7.5 55. 1.25 1.50 327. 1001600200068 7.5 55. 1.50 1.75 220. 1001600200069 7.5 55. 1.75 2.00 133. 1001600200070 7.5 55. 2.00 2.25 103. 1001600200071 7.5 55. 2.25 2.50 74. 1001600200072 7.5 55. 2.50 2.75 55. 1001600200073 7.5 55. 2.75 3.00 38. 1001600200074 7.5 55. 3.00 3.25 30. 1001600200075 7.5 55. 3.25 3.50 25. 1001600200076 7.5 55. 3.50 3.75 20. 1001600200077 7.5 55. 3.75 4.00 14. 1001600200078 7.5 55. 4.00 4.25 11. 1001600200079 7.5 55. 4.25 4.50 6. 1001600200080 7.5 55. 4.50 4.75 5. 1001600200081 7.5 55. 4.75 5.00 3. 1001600200082 ENDDATA 75 0 1001600200083 ENDSUBENT 82 0 1001600299999 NOSUBENT 10016003 19800813 00001001600300001 NOSUBENT 10016004 19800813 00001001600400001 NOSUBENT 10016005 19800813 00001001600500001 SUBENT 10016006 19990617 00001001600600001 BIB 6 9 1001600600002 REACTION (92-U-235(N,INL)92-U-235,,SIG) 1001600600003 METHOD Calculated from the integrated gamma emission spectra 1001600600004 using total gamma en/nonelastic collision = 1001600600005 ((7.5 x fission cs) + (inelastic cs)(neut,en. - 2T))/1001600600006 (gamma emission cs) , where T = nuclear temperature.1001600600007 ASSUMED (ASSUM,92-U-235(N,F),,SIG) 1001600600008 MISC-COL (MISC) Value of 2T used in formula given under method. 1001600600009 STATUS (DEP,10016002) 1001600600010 HISTORY (19860825A) REACTION corrected. 1001600600011 ENDBIB 9 0 1001600600012 NOCOMMON 0 0 1001600600013 DATA 5 3 1001600600014 EN DATA DATA-ERR ASSUM MISC 1001600600015 MEV B B B MEV 1001600600016 4.0 2.13 0.50 1.10 0.75 1001600600017 6.0 2.02 0.36 1.06 0.94 1001600600018 7.5 0.77 0.32 1.60 1.06 1001600600019 ENDDATA 5 0 1001600600020 ENDSUBENT 19 0 1001600699999 ENDENTRY 6 0 1001699999999