ENTRY 21086 20230130 231321086 0 1 SUBENT 21086001 20230130 231321086 1 1 BIB 14 31 21086 1 2 TITLE Inelastic scattering of fast neutrons by U-235 21086 1 3 AUTHOR (B.H.Armitage,A.T.G.Ferguson,J.H.Montague,N.Starfelt) 21086 1 4 REFERENCE (C,66PARIS,1,383,1966) 21086 1 5 (C,66OXFORD,,1,1966) Same as 66PARIS. 21086 1 6 (P,AERE-PR/NP-7,1(1),1964) 21086 1 7 (P,AERE-PR/NP-6,1(2),1963) 21086 1 8 INSTITUTE (2UK HAR) 21086 1 9 (2SWDAE ) N.S on leave. 21086 1 10 FACILITY (VDG,2UK HAR) IBIS 3 MeV Van der Graaff. 21086 1 11 INC-SOURCE (P-LI7) Pulsed proton bombardment of thick lithium. 21086 1 12 (P-T) and tritium gas targets, to produce 21086 1 13 monoenergetic neutrons. 21086 1 14 SAMPLE (92-U-235,ENR=0.97) Metal. Two samples, 0.5 inch 21086 1 15 diameter, 1.0 inch long. 0.6 Inch diameter, 1.2 inch 21086 1 16 long. 21086 1 17 METHOD (TOF) 150 cm from scattering sample to detector. 21086 1 18 DETECTOR (SCIN) Plastic scintillator, 10 cm diameter, 2.5 cm 21086 1 19 thick, with threshold to minimize background. 21086 1 20 MONITOR (6-C-12(N,EL)6-C-12,,SIG) 21086 1 21 MONIT-REF (10415007,R.O.Lane+,J,AP,12,135,1961) 21086 1 22 CORRECTION Corrected for background, elastic scattered 21086 1 23 spectrum from lead sample used to separate the 21086 1 24 elastic and inelastic scattering from U-235. 21086 1 25 Corrected for sample attenuation and multiple 21086 1 26 scattering by monte-carlo calculation. 21086 1 27 ERR-ANALYS (DATA-ERR) Errors mainly are systematic, statistical 21086 1 28 errors are considered negligible. 21086 1 29 HISTORY (19790905C) 21086 1 30 (19800108A) Recompiled from table I, 66PARIS 21086 1 31 (20230130A) SD:Updated to new date formats,lower case. 21086 1 32 Corrections in all Subents. 21086 1 33 ENDBIB 31 0 21086 1 34 COMMON 1 3 21086 1 35 ANG 21086 1 36 ADEG 21086 1 37 90. 21086 1 38 ENDCOMMON 3 0 21086 1 39 ENDSUBENT 38 0 21086 199999 SUBENT 21086002 20230130 231321086 2 1 BIB 4 10 21086 2 2 REACTION (92-U-235(N,EL)92-U-235,,DA) 21086 2 3 CRITIQUE Stanislav Simakov (2022-06-03): The Pb-shape peak 21086 2 4 subtraction of inelastically scattered neutrons 21086 2 5 probably not valid for the first level of 235U with 21086 2 6 excitation energy 0.08 keV which is substantially 21086 2 7 lower than energy resolution 25 keV. 21086 2 8 STATUS (CURVE) Fig. 3 from 66PARIS,383 21086 2 9 HISTORY (20230130A) SD: SF8=4PI deleted from REACTION code 21086 2 10 according to description at the bottom of the fig.3. 21086 2 11 CRITUQUE added. 21086 2 12 ENDBIB 10 0 21086 2 13 COMMON 2 3 21086 2 14 EN-ERR-DIG ERR-DIG 21086 2 15 MEV B/SR 21086 2 16 0.002 0.001 21086 2 17 ENDCOMMON 3 0 21086 2 18 DATA 3 7 21086 2 19 EN DATA DATA-ERR 21086 2 20 MEV B/SR B/SR 21086 2 21 0.124 0.734 0.071 21086 2 22 0.398 0.381 0.039 21086 2 23 0.546 0.280 0.030 21086 2 24 0.697 0.236 0.025 21086 2 25 1.000 0.185 0.020 21086 2 26 1.501 0.188 0.019 21086 2 27 1.899 0.188 0.017 21086 2 28 ENDDATA 9 0 21086 2 29 ENDSUBENT 28 0 21086 299999 SUBENT 21086003 20230130 231321086 3 1 BIB 3 4 21086 3 2 REACTION (92-U-235(N,INL)92-U-235,PAR,DA,,4PI) 21086 3 3 STATUS (TABLE) Table 1 from 66PARIS,383 21086 3 4 HISTORY (19800108A) Recompiled from table I, 66PARIS 21086 3 5 (20230130A) SD: E-MIN/MAX -> E-EXC-MIN/MAX. 21086 3 6 ENDBIB 4 0 21086 3 7 COMMON 1 3 21086 3 8 DATA-ERR 21086 3 9 PER-CENT 21086 3 10 2.0000E+01 21086 3 11 ENDCOMMON 3 0 21086 3 12 DATA 4 48 21086 3 13 EN E-EXC-MIN E-EXC-MAX DATA 21086 3 14 KEV KEV KEV MB 21086 3 15 130. 0. 25. 344. 21086 3 16 130. 25. 50. 238. 21086 3 17 400. 0. 25. 37. 21086 3 18 400. 25. 50. 306. 21086 3 19 400. 50. 100. 616. 21086 3 20 400. 100. 150. 327. 21086 3 21 400. 150. 200. 184. 21086 3 22 400. 200. 300. 350. 21086 3 23 550. 25. 50. 92. 21086 3 24 550. 50. 100. 314. 21086 3 25 550. 100. 150. 224. 21086 3 26 550. 150. 200. 236. 21086 3 27 550. 200. 300. 203. 21086 3 28 550. 300. 400. 229. 21086 3 29 550. 400. 500. 66. 21086 3 30 710. 25. 50. 45. 21086 3 31 710. 50. 100. 211. 21086 3 32 710. 100. 150. 221. 21086 3 33 710. 150. 200. 191. 21086 3 34 710. 200. 300. 245. 21086 3 35 710. 300. 400. 285. 21086 3 36 710. 400. 500. 359. 21086 3 37 710. 500. 600. 206. 21086 3 38 1000. 50. 100. 182. 21086 3 39 1000. 100. 150. 178. 21086 3 40 1000. 150. 200. 130. 21086 3 41 1000. 200. 300. 166. 21086 3 42 1000. 300. 400. 187. 21086 3 43 1000. 400. 500. 177. 21086 3 44 1000. 500. 600. 126. 21086 3 45 1000. 600. 700. 172. 21086 3 46 1000. 700. 800. 157. 21086 3 47 1000. 800. 900. 89. 21086 3 48 1500. 50. 100. 90. 21086 3 49 1500. 100. 150. 159. 21086 3 50 1500. 150. 200. 102. 21086 3 51 1500. 200. 300. 94. 21086 3 52 1500. 300. 400. 68. 21086 3 53 1500. 400. 500. 47. 21086 3 54 1500. 500. 600. 48. 21086 3 55 1500. 600. 700. 69. 21086 3 56 1500. 700. 800. 94. 21086 3 57 1500. 800. 900. 121. 21086 3 58 1500. 900. 1000. 159. 21086 3 59 1500. 1000. 1100. 195. 21086 3 60 1500. 1100. 1200. 166. 21086 3 61 1500. 1200. 1300. 110. 21086 3 62 1550. 1300. 1400. 54. 21086 3 63 ENDDATA 50 0 21086 3 64 ENDSUBENT 63 0 21086 399999 SUBENT 21086004 20230130 231321086 4 1 BIB 4 5 21086 4 2 REACTION (92-U-235(N,INL)92-U-235,PAR,DA,,4PI) 21086 4 3 ANALYSIS (INTED) Integrated secondary neutron energy distribut. 21086 4 4 STATUS (TABLE) Table 1 from 66PARIS,383 21086 4 5 HISTORY (19800108A) Recompiled from table I, 66PARIS 21086 4 6 (20230130A) SD: E-MIN/MAX -> E-EXC-MIN/MAX. 21086 4 7 ENDBIB 5 0 21086 4 8 COMMON 1 3 21086 4 9 DATA-ERR 21086 4 10 PER-CENT 21086 4 11 10. 21086 4 12 ENDCOMMON 3 0 21086 4 13 DATA 3 6 21086 4 14 EN E-EXC-MIN DATA 21086 4 15 KEV KEV MB 21086 4 16 130. 70. 582. 21086 4 17 400. 170. 1820. 21086 4 18 550. 110. 1364. 21086 4 19 710. 130. 1763. 21086 4 20 1000. 130. 1564. 21086 4 21 1500. 140. 1576. 21086 4 22 ENDDATA 8 0 21086 4 23 ENDSUBENT 22 0 21086 499999 ENDENTRY 4 0 2108699999999