ENTRY 21725 20230130 2172500000001 SUBENT 21725001 20230130 20231011 2172500100001 BIB 11 47 2172500100002 TITLE Study of the interaction of 14 MeV neutrons with U-238 2172500100003 AUTHOR (J.Voignier) 2172500100004 REFERENCE (R,CEA-R-3503,1968) in French 2172500100005 (C,67BORDEAUX,,24,1967) Abstract. 2172500100006 INSTITUTE (2FR VNV) Centre d'Etudes de Limeil. 2172500100007 FACILITY (ACCEL,2FR VNV) Accelerator HAEFELY, providing 2172500100008 200 keV deuterons. 2172500100009 INC-SOURCE (D-T) Producing 1.E7 to 2.E7 neutrons/sec. 2172500100010 SAMPLE Cylinders of natural uranium, thickness 5 cm, 2172500100011 diameter 5 or 10 cm. 2172500100012 METHOD (ASSOP) Associated alpha particles from d-T 2172500100013 reaction are detected at 45. or 135. degrees with 2172500100014 respect to the deuteron beam. 2172500100015 (TOF) Between the detection of the associated 2172500100016 alpha and the detection of the neutrons. 2172500100017 (COINC) Between the neutron and the associated alpha. 2172500100018 The total cross section was measured with the 2172500100019 transmission method. The other cross sections 2172500100020 were measured by detection of the scattered 2172500100021 neutrons or were derived quantities. 2172500100022 DETECTOR (SCIN) Plastic scintillator, 0.1 mm thick viewed by a 2172500100023 56AVP Pm-tube at 15 cm from the target for the 2172500100024 detection of the associated alphas. 2172500100025 (SCIN) Liquid scintillator NE102 viewed by a 56AVP Pm- 2172500100026 tube at 1.20 m from the scatterer to detect the 2172500100027 scattered neutrons. Two cylindrical scintillators 2172500100028 were used (diam. = 5 cm, thickness = 5 cm) and 2172500100029 (diam. = 10 cm, thickness = 5 cm). No details given 2172500100030 about the detector used for the transmission 2172500100031 measurements. In the scattering measurements also a 2172500100032 solid detector was used to monitor the alpha particles.2172500100033 ERR-ANALYS (ERR-T) Total error includes: 2172500100034 * An error from the correction for the 2172500100035 neutron flux attenuation in the scatterer. 2172500100036 * Statistical error including the completely 2172500100037 uncorrelated uncertainty from the background 2172500100038 subtraction. 2172500100039 (ERR-1) Detector efficiency at 14.1 MeV (outcoming 2172500100040 neutron energy). 2172500100041 (ERR-2,,3.4) Error on associated alpha particle 2172500100042 monitoring. This error may contain both a statistical 2172500100043 (counting statistics in the run with the neutron 2172500100044 detector at a specific angle) and a sytematic part 2172500100045 (counting statistics of the reference run). 2172500100046 HISTORY (19810209C) G.C. 2172500100047 (20230130A) SD:Updated to new date formats,lower case. 2172500100048 Corrections in all Subents. 2172500100049 ENDBIB 47 0 2172500100050 COMMON 3 3 2172500100051 EN EN-RSL ERR-1 2172500100052 MEV MEV PER-CENT 2172500100053 14.1 0.1 9.6 2172500100054 ENDCOMMON 3 0 2172500100055 ENDSUBENT 54 0 2172500199999 SUBENT 21725002 20230130 20231011 2172500200001 BIB 5 9 2172500200002 REACTION (92-U-238(N,TOT),,SIG) 2172500200003 CORRECTION For 'inscattering' (see COMMENT). 2172500200004 COMMENT The detector additionally to transmitted neutrons 2172500200005 received elastically scattered neutrons from the 2172500200006 target. Counting these neutrons is a measurement error 2172500200007 that results in a reduction in the calculated total 2172500200008 cross section. 2172500200009 STATUS (TABLE) Text on p.14 of CEA-R-3503,1968 2172500200010 HISTORY (20230130U) SD: BIB updated. 2172500200011 ENDBIB 9 0 2172500200012 NOCOMMON 0 0 2172500200013 DATA 2 1 2172500200014 DATA ERR-T 2172500200015 B B 2172500200016 5.85 0.18 2172500200017 ENDDATA 3 0 2172500200018 ENDSUBENT 17 0 2172500299999 SUBENT 21725003 20230130 20231011 2172500300001 BIB 9 14 2172500300002 REACTION (92-U-238(N,EL)92-U-238,EXL,SIG) 2172500300003 SAMPLE Natural U. 2172500300004 ANALYSIS (INTAD) Integrated angular distribution. 2172500300005 COMMENT The angular distribution was extrapolated below 2172500300006 20 degrees and above 150 degrees. 2172500300007 CRITIQUE S.Simakov (2022-08-06): Possible inclusion of inelastic2172500300008 scattering below Ex ~ 2 MeV. 2172500300009 REL-REF (C,,S.Simakov+,S,INDC(NDS)-0857,91,2022) 2172500300010 CORRECTION Background. 2172500300011 Neutron flux fluctuations. 2172500300012 STATUS (TABLE) Text on p.23 of CEA-R-3503,1968 2172500300013 (DEP,21725004) Integration of angular distributions 2172500300014 in Subent 004. 2172500300015 HISTORY (20230130A) SD: SF5=EXL added to REACTION code. 2172500300016 ENDBIB 14 0 2172500300017 NOCOMMON 0 0 2172500300018 DATA 2 1 2172500300019 DATA ERR-T 2172500300020 B B 2172500300021 2.96 0.23 2172500300022 ENDDATA 3 0 2172500300023 ENDSUBENT 22 0 2172500399999 SUBENT 21725004 20230130 20231011 2172500400001 BIB 6 10 2172500400002 REACTION (92-U-238(N,EL)92-U-238,EXL,DA) 2172500400003 CORRECTION N-flux fluctuations. 2172500400004 Background. 2172500400005 CRITIQUE S.Simakov (2022-08-06): Possible inclusion of inelastic2172500400006 scattering below Ex ~ 2 MeV. 2172500400007 REL-REF (C,,S.Simakov+,S,INDC(NDS)-0857,91,2022) 2172500400008 STATUS (TABLE) Table 1 on p.23 of CEA-R-3503,1968 2172500400009 (DEP,21725004) Integration of angular distributions 2172500400010 in Subent 004. 2172500400011 HISTORY (20230130A) SD: SF5=EXL added to REACTION code. 2172500400012 ENDBIB 10 0 2172500400013 COMMON 1 3 2172500400014 ANG-RSL 2172500400015 PER-CENT 2172500400016 3. 2172500400017 ENDCOMMON 3 0 2172500400018 DATA 3 15 2172500400019 ANG DATA ERR-T 2172500400020 ADEG MB/SR MB/SR 2172500400021 20. 1200. 73. 2172500400022 25. 415. 23. 2172500400023 30. 460. 26. 2172500400024 40. 475. 27. 2172500400025 50. 129. 8. 2172500400026 60. 100. 6. 2172500400027 70. 80. 5. 2172500400028 80. 32. 3. 2172500400029 90. 32. 3. 2172500400030 100. 19. 2. 2172500400031 110. 13.1 1.3 2172500400032 120. 13.9 1.4 2172500400033 130. 10.4 0.8 2172500400034 140. 10.5 1.2 2172500400035 150. 8.3 1.1 2172500400036 ENDDATA 17 0 2172500400037 ENDSUBENT 36 0 2172500499999 SUBENT 21725005 20230130 20231011 2172500500001 BIB 6 18 2172500500002 REACTION (92-U-238(N,NON),,SIG,,,DERIV) 2172500500003 ANALYSIS Obtained as difference between the total cross 2172500500004 section and the elastic scattering cross section. 2172500500005 CORRECTION Neutron flux fluctuations. 2172500500006 Background. 2172500500007 subtraction of elastic peak. 2172500500008 'inscattering' in total cross section measurement (see2172500500009 COMMENT). 2172500500010 COMMENT The detector additionally to transmitted neutrons 2172500500011 received elastically scattered neutrons from the 2172500500012 target. Counting these neutrons is a measurement error 2172500500013 that results in a reduction in the calculated total 2172500500014 cross section. 2172500500015 STATUS (TABLE) Text on p.25 of CEA-R-3503,1968 2172500500016 (DEP,21725002) 2172500500017 (DEP,21725003) 2172500500018 HISTORY (20230130A) SD: SF9=DERIV added to REACTION code. 2172500500019 BIB updated. 2172500500020 ENDBIB 18 0 2172500500021 NOCOMMON 0 0 2172500500022 DATA 2 1 2172500500023 DATA ERR-T 2172500500024 B B 2172500500025 2.89 0.24 2172500500026 ENDDATA 3 0 2172500500027 ENDSUBENT 26 0 2172500599999 SUBENT 21725006 20230130 20231011 2172500600001 BIB 4 6 2172500600002 REACTION (92-U-238(N,X)0-NN-1,EM,DA/DE) 2172500600003 CORRECTION Background. 2172500600004 Neutron flux fluctuations. 2172500600005 Elastic peak. 2172500600006 STATUS (TABLE) Tables 2-8 on p.23 of CEA-R-3503,1968 2172500600007 HISTORY (20230130U) SD: BIB updated. 2172500600008 ENDBIB 6 0 2172500600009 COMMON 1 3 2172500600010 ANG-RSL 2172500600011 PER-CENT 2172500600012 3. 2172500600013 ENDCOMMON 3 0 2172500600014 DATA 6 97 2172500600015 ANG E-MIN E-MAX DATA ERR-T ERR-S 2172500600016 ADEG MEV MEV MB/SR/MEV MB/SR/MEV PER-CENT 2172500600017 25. 1. 2. 186. 19. 2.82172500600018 25. 2. 3. 91. 9. 2.92172500600019 25. 3. 4. 36. 4. 4.72172500600020 25. 4. 5. 20. 2.5 7.22172500600021 25. 5. 6. 12. 1.7 10.72172500600022 25. 6. 7. 7.3 1.3 15.62172500600023 25. 7. 8. 4.8 1.1 22.2172500600024 30. 1. 2. 193. 20. 2.52172500600025 30. 2. 3. 104. 11. 2.42172500600026 30. 3. 4. 43. 4.6 4.2172500600027 30. 4. 5. 22. 2.6 6.2172500600028 30. 5. 6. 13. 1.7 9.2172500600029 30. 6. 7. 7.6 1.3 13.32172500600030 30. 7. 8. 5. 1. 19.2172500600031 40. 1. 1. 201. 21. 2.62172500600032 40. 2. 3. 102. 11. 3.2172500600033 40. 3. 4. 42. 4.7 4.72172500600034 40. 4. 5. 21.5 2.8 10.2172500600035 40. 5. 6. 12.4 1.8 10.2172500600036 40. 6. 7. 7.5 1.3 14.2172500600037 40. 7. 8. 4.8 1. 19.2172500600038 50. 1. 2. 191. 20. 2.22172500600039 50. 2. 3. 85. 9. 2.52172500600040 50. 3. 4. 35. 4. 4.12172500600041 50. 4. 5. 18.5 2.2 6.22172500600042 50. 5. 6. 10.8 1.5 9.32172500600043 50. 6. 7. 6.7 1.1 13.22172500600044 50. 7. 8. 4.5 0.9 18.2172500600045 60. 1. 2. 180. 19. 2.12172500600046 60. 2. 3. 85. 9. 2.32172500600047 60. 3. 4. 35. 4. 3.82172500600048 60. 4. 5. 19.5 2.2 5.42172500600049 60. 5. 6. 10.7 1.4 8.32172500600050 60. 6. 7. 6.6 1.4 8.32172500600051 60. 7. 8. 4.4 0.8 16.62172500600052 70. 1. 2. 166. 17. 1.92172500600053 70. 2. 3. 69. 7.2 2.22172500600054 70. 3. 4. 30. 3.2 3.52172500600055 70. 4. 5. 16.5 1.8 5.22172500600056 70. 5. 6. 9. 1.1 8.2172500600057 70. 6. 7. 5.5 0.8 11.52172500600058 70. 7. 8. 3.6 0.7 16.2172500600059 80. 1. 2. 140. 15. 2.12172500600060 80. 2. 3. 80. 8. 1.92172500600061 80. 3. 4. 37. 4. 2.82172500600062 80. 4. 5. 22. 2.3 3.92172500600063 80. 5. 6. 12.2 1.4 5.82172500600064 80. 6. 7. 7.8 1. 7.82172500600065 80. 7. 8. 5.1 0.7 10.92172500600066 90. 1. 2. 160. 16. 1.62172500600067 90. 2. 3. 74. 8. 1.82172500600068 90. 3. 4. 35. 4. 2.72172500600069 90. 4. 5. 18. 2. 4.2172500600070 90. 5. 6. 10.8 1.2 5.72172500600071 90. 6. 7. 7.3 0.9 7.42172500600072 90. 7. 8. 5. 0.7 9.82172500600073 100. 1. 2. 153. 17. 2.2172500600074 100. 2. 3. 74. 7. 2.12172500600075 100. 3. 4. 35. 4. 3.12172500600076 100. 4. 5. 19. 2. 4.42172500600077 100. 5. 6. 11. 1.3 6.62172500600078 100. 6. 7. 7. 0.9 8.82172500600079 100. 7. 8. 4.4 0.7 12.52172500600080 110. 1. 2. 160. 16. 1.72172500600081 110. 2. 3. 73. 8. 2.2172500600082 110. 3. 4. 33.4 3.5 2.92172500600083 110. 4. 5. 17.7 2. 4.32172500600084 110. 5. 6. 10.7 1.2 6.12172500600085 110. 6. 7. 7. 0.9 8.22172500600086 110. 7. 8. 3.6 0.6 13.92172500600087 120. 1. 2. 173. 18. 1.92172500600088 120. 2. 3. 81. 8. 2.12172500600089 120. 3. 4. 39. 4. 3.2172500600090 120. 4. 5. 20.5 2.3 4.72172500600091 120. 5. 6. 10.3 1.3 7.32172500600092 120. 6. 7. 6.8 0.9 9.72172500600093 120. 7. 8. 4.3 0.7 14.2172500600094 130. 1. 2. 183. 19. 1.92172500600095 130. 2. 3. 81. 8. 2.12172500600096 130. 3. 4. 38. 4. 3.22172500600097 130. 4. 5. 20.5 2.3 4.72172500600098 130. 5. 6. 11.4 1.4 7.2172500600099 130. 6. 7. 6.7 1. 10.32172500600100 130. 7. 8. 4.4 0.8 14.52172500600101 140. 1. 2. 174. 18. 1.92172500600102 140. 2. 3. 76. 8. 2.22172500600103 140. 3. 4. 37. 4. 3.22172500600104 140. 4. 5. 20. 2. 4.72172500600105 140. 5. 6. 12.5 1.5 6.42172500600106 140. 6. 7. 7.2 1. 9.52172500600107 140. 7. 8. 4.6 0.7 13.72172500600108 150. 1. 2. 172. 18. 2.32172500600109 150. 2. 3. 74. 8. 2.72172500600110 150. 3. 4. 35. 4. 3.92172500600111 150. 4. 5. 20. 2.3 5.62172500600112 150. 5. 6. 12.3 1.5 7.82172500600113 150. 6. 7. 6.5 1. 12.72172500600114 ENDDATA 99 0 2172500600115 ENDSUBENT 114 0 2172500699999 SUBENT 21725007 20230130 20231011 2172500700001 BIB 5 10 2172500700002 REACTION (92-U-238(N,X)0-NN-1,EM,SIG) 2172500700003 ANALYSIS (INTAD,INTED) Integration of the data from 2172500700004 Subent 006, by extrapolation to 0. energy 2172500700005 and below 25 degr. and above 150. degr. 2172500700006 CORRECTION Background. 2172500700007 Neutron flux fluctuations. 2172500700008 Elastic peak. 2172500700009 STATUS (TABLE) Text on p.42 of CEA-R-3503,1968 2172500700010 (DEP,21725006) Derived from Subent 006. 2172500700011 HISTORY (20230130U) SD: BIB updated. 2172500700012 ENDBIB 10 0 2172500700013 NOCOMMON 0 0 2172500700014 DATA 2 1 2172500700015 DATA ERR-T 2172500700016 B B 2172500700017 8.47 0.72 2172500700018 ENDDATA 3 0 2172500700019 ENDSUBENT 18 0 2172500799999 ENDENTRY 7 0 2172599999999