ENTRY 21725 20230130 231321725 0 1 SUBENT 21725001 20230130 231321725 1 1 BIB 11 47 21725 1 2 TITLE Study of the interaction of 14 MeV neutrons with U-238 21725 1 3 AUTHOR (J.Voignier) 21725 1 4 REFERENCE (R,CEA-R-3503,1968) in French 21725 1 5 (C,67BORDEAUX,,24,1967) Abstract. 21725 1 6 INSTITUTE (2FR VNV) Centre d'Etudes de Limeil. 21725 1 7 FACILITY (ACCEL,2FR VNV) Accelerator HAEFELY, providing 21725 1 8 200 keV deuterons. 21725 1 9 INC-SOURCE (D-T) Producing 1.E7 to 2.E7 neutrons/sec. 21725 1 10 SAMPLE Cylinders of natural uranium, thickness 5 cm, 21725 1 11 diameter 5 or 10 cm. 21725 1 12 METHOD (ASSOP) Associated alpha particles from d-T 21725 1 13 reaction are detected at 45. or 135. degrees with 21725 1 14 respect to the deuteron beam. 21725 1 15 (TOF) Between the detection of the associated 21725 1 16 alpha and the detection of the neutrons. 21725 1 17 (COINC) Between the neutron and the associated alpha. 21725 1 18 The total cross section was measured with the 21725 1 19 transmission method. The other cross sections 21725 1 20 were measured by detection of the scattered 21725 1 21 neutrons or were derived quantities. 21725 1 22 DETECTOR (SCIN) Plastic scintillator, 0.1 mm thick viewed by a 21725 1 23 56AVP Pm-tube at 15 cm from the target for the 21725 1 24 detection of the associated alphas. 21725 1 25 (SCIN) Liquid scintillator NE102 viewed by a 56AVP Pm- 21725 1 26 tube at 1.20 m from the scatterer to detect the 21725 1 27 scattered neutrons. Two cylindrical scintillators 21725 1 28 were used (diam. = 5 cm, thickness = 5 cm) and 21725 1 29 (diam. = 10 cm, thickness = 5 cm). No details given 21725 1 30 about the detector used for the transmission 21725 1 31 measurements. In the scattering measurements also a 21725 1 32 solid detector was used to monitor the alpha particles.21725 1 33 ERR-ANALYS (ERR-T) Total error includes: 21725 1 34 * An error from the correction for the 21725 1 35 neutron flux attenuation in the scatterer. 21725 1 36 * Statistical error including the completely 21725 1 37 uncorrelated uncertainty from the background 21725 1 38 subtraction. 21725 1 39 (ERR-1) Detector efficiency at 14.1 MeV (outcoming 21725 1 40 neutron energy). 21725 1 41 (ERR-2,,3.4) Error on associated alpha particle 21725 1 42 monitoring. This error may contain both a statistical 21725 1 43 (counting statistics in the run with the neutron 21725 1 44 detector at a specific angle) and a sytematic part 21725 1 45 (counting statistics of the reference run). 21725 1 46 HISTORY (19810209C) G.C. 21725 1 47 (20230130A) SD:Updated to new date formats,lower case. 21725 1 48 Corrections in all Subents. 21725 1 49 ENDBIB 47 0 21725 1 50 COMMON 3 3 21725 1 51 EN EN-RSL ERR-1 21725 1 52 MEV MEV PER-CENT 21725 1 53 14.1 0.1 9.6 21725 1 54 ENDCOMMON 3 0 21725 1 55 ENDSUBENT 54 0 21725 199999 SUBENT 21725002 20230130 231321725 2 1 BIB 5 9 21725 2 2 REACTION (92-U-238(N,TOT),,SIG) 21725 2 3 CORRECTION For 'inscattering' (see COMMENT). 21725 2 4 COMMENT The detector additionally to transmitted neutrons 21725 2 5 received elastically scattered neutrons from the 21725 2 6 target. Counting these neutrons is a measurement error 21725 2 7 that results in a reduction in the calculated total 21725 2 8 cross section. 21725 2 9 STATUS (TABLE) Text on p.14 of CEA-R-3503,1968 21725 2 10 HISTORY (20230130U) SD: BIB updated. 21725 2 11 ENDBIB 9 0 21725 2 12 NOCOMMON 0 0 21725 2 13 DATA 2 1 21725 2 14 DATA ERR-T 21725 2 15 B B 21725 2 16 5.85 0.18 21725 2 17 ENDDATA 3 0 21725 2 18 ENDSUBENT 17 0 21725 299999 SUBENT 21725003 20230130 231321725 3 1 BIB 9 14 21725 3 2 REACTION (92-U-238(N,EL)92-U-238,EXL,SIG) 21725 3 3 SAMPLE Natural U. 21725 3 4 ANALYSIS (INTAD) Integrated angular distribution. 21725 3 5 COMMENT The angular distribution was extrapolated below 21725 3 6 20 degrees and above 150 degrees. 21725 3 7 CRITIQUE S.Simakov (2022-08-06): Possible inclusion of inelastic21725 3 8 scattering below Ex ~ 2 MeV. 21725 3 9 REL-REF (C,,S.Simakov+,S,INDC(NDS)-0857,91,2022) 21725 3 10 CORRECTION Background. 21725 3 11 Neutron flux fluctuations. 21725 3 12 STATUS (TABLE) Text on p.23 of CEA-R-3503,1968 21725 3 13 (DEP,21725004) Integration of angular distributions 21725 3 14 in Subent 004. 21725 3 15 HISTORY (20230130A) SD: SF5=EXL added to REACTION code. 21725 3 16 ENDBIB 14 0 21725 3 17 NOCOMMON 0 0 21725 3 18 DATA 2 1 21725 3 19 DATA ERR-T 21725 3 20 B B 21725 3 21 2.96 0.23 21725 3 22 ENDDATA 3 0 21725 3 23 ENDSUBENT 22 0 21725 399999 SUBENT 21725004 20230130 231321725 4 1 BIB 6 10 21725 4 2 REACTION (92-U-238(N,EL)92-U-238,EXL,DA) 21725 4 3 CORRECTION N-flux fluctuations. 21725 4 4 Background. 21725 4 5 CRITIQUE S.Simakov (2022-08-06): Possible inclusion of inelastic21725 4 6 scattering below Ex ~ 2 MeV. 21725 4 7 REL-REF (C,,S.Simakov+,S,INDC(NDS)-0857,91,2022) 21725 4 8 STATUS (TABLE) Table 1 on p.23 of CEA-R-3503,1968 21725 4 9 (DEP,21725004) Integration of angular distributions 21725 4 10 in Subent 004. 21725 4 11 HISTORY (20230130A) SD: SF5=EXL added to REACTION code. 21725 4 12 ENDBIB 10 0 21725 4 13 COMMON 1 3 21725 4 14 ANG-RSL 21725 4 15 PER-CENT 21725 4 16 3. 21725 4 17 ENDCOMMON 3 0 21725 4 18 DATA 3 15 21725 4 19 ANG DATA ERR-T 21725 4 20 ADEG MB/SR MB/SR 21725 4 21 20. 1200. 73. 21725 4 22 25. 415. 23. 21725 4 23 30. 460. 26. 21725 4 24 40. 475. 27. 21725 4 25 50. 129. 8. 21725 4 26 60. 100. 6. 21725 4 27 70. 80. 5. 21725 4 28 80. 32. 3. 21725 4 29 90. 32. 3. 21725 4 30 100. 19. 2. 21725 4 31 110. 13.1 1.3 21725 4 32 120. 13.9 1.4 21725 4 33 130. 10.4 0.8 21725 4 34 140. 10.5 1.2 21725 4 35 150. 8.3 1.1 21725 4 36 ENDDATA 17 0 21725 4 37 ENDSUBENT 36 0 21725 499999 SUBENT 21725005 20230130 231321725 5 1 BIB 6 18 21725 5 2 REACTION (92-U-238(N,NON),,SIG,,,DERIV) 21725 5 3 ANALYSIS Obtained as difference between the total cross 21725 5 4 section and the elastic scattering cross section. 21725 5 5 CORRECTION Neutron flux fluctuations. 21725 5 6 Background. 21725 5 7 subtraction of elastic peak. 21725 5 8 'inscattering' in total cross section measurement (see21725 5 9 COMMENT). 21725 5 10 COMMENT The detector additionally to transmitted neutrons 21725 5 11 received elastically scattered neutrons from the 21725 5 12 target. Counting these neutrons is a measurement error 21725 5 13 that results in a reduction in the calculated total 21725 5 14 cross section. 21725 5 15 STATUS (TABLE) Text on p.25 of CEA-R-3503,1968 21725 5 16 (DEP,21725002) 21725 5 17 (DEP,21725003) 21725 5 18 HISTORY (20230130A) SD: SF9=DERIV added to REACTION code. 21725 5 19 BIB updated. 21725 5 20 ENDBIB 18 0 21725 5 21 NOCOMMON 0 0 21725 5 22 DATA 2 1 21725 5 23 DATA ERR-T 21725 5 24 B B 21725 5 25 2.89 0.24 21725 5 26 ENDDATA 3 0 21725 5 27 ENDSUBENT 26 0 21725 599999 SUBENT 21725006 20230130 231321725 6 1 BIB 4 6 21725 6 2 REACTION (92-U-238(N,X)0-NN-1,EM,DA/DE) 21725 6 3 CORRECTION Background. 21725 6 4 Neutron flux fluctuations. 21725 6 5 Elastic peak. 21725 6 6 STATUS (TABLE) Tables 2-8 on p.23 of CEA-R-3503,1968 21725 6 7 HISTORY (20230130U) SD: BIB updated. 21725 6 8 ENDBIB 6 0 21725 6 9 COMMON 1 3 21725 6 10 ANG-RSL 21725 6 11 PER-CENT 21725 6 12 3. 21725 6 13 ENDCOMMON 3 0 21725 6 14 DATA 6 97 21725 6 15 ANG E-MIN E-MAX DATA ERR-T ERR-S 21725 6 16 ADEG MEV MEV MB/SR/MEV MB/SR/MEV PER-CENT 21725 6 17 25. 1. 2. 186. 19. 2.821725 6 18 25. 2. 3. 91. 9. 2.921725 6 19 25. 3. 4. 36. 4. 4.721725 6 20 25. 4. 5. 20. 2.5 7.221725 6 21 25. 5. 6. 12. 1.7 10.721725 6 22 25. 6. 7. 7.3 1.3 15.621725 6 23 25. 7. 8. 4.8 1.1 22.21725 6 24 30. 1. 2. 193. 20. 2.521725 6 25 30. 2. 3. 104. 11. 2.421725 6 26 30. 3. 4. 43. 4.6 4.21725 6 27 30. 4. 5. 22. 2.6 6.21725 6 28 30. 5. 6. 13. 1.7 9.21725 6 29 30. 6. 7. 7.6 1.3 13.321725 6 30 30. 7. 8. 5. 1. 19.21725 6 31 40. 1. 1. 201. 21. 2.621725 6 32 40. 2. 3. 102. 11. 3.21725 6 33 40. 3. 4. 42. 4.7 4.721725 6 34 40. 4. 5. 21.5 2.8 10.21725 6 35 40. 5. 6. 12.4 1.8 10.21725 6 36 40. 6. 7. 7.5 1.3 14.21725 6 37 40. 7. 8. 4.8 1. 19.21725 6 38 50. 1. 2. 191. 20. 2.221725 6 39 50. 2. 3. 85. 9. 2.521725 6 40 50. 3. 4. 35. 4. 4.121725 6 41 50. 4. 5. 18.5 2.2 6.221725 6 42 50. 5. 6. 10.8 1.5 9.321725 6 43 50. 6. 7. 6.7 1.1 13.221725 6 44 50. 7. 8. 4.5 0.9 18.21725 6 45 60. 1. 2. 180. 19. 2.121725 6 46 60. 2. 3. 85. 9. 2.321725 6 47 60. 3. 4. 35. 4. 3.821725 6 48 60. 4. 5. 19.5 2.2 5.421725 6 49 60. 5. 6. 10.7 1.4 8.321725 6 50 60. 6. 7. 6.6 1.4 8.321725 6 51 60. 7. 8. 4.4 0.8 16.621725 6 52 70. 1. 2. 166. 17. 1.921725 6 53 70. 2. 3. 69. 7.2 2.221725 6 54 70. 3. 4. 30. 3.2 3.521725 6 55 70. 4. 5. 16.5 1.8 5.221725 6 56 70. 5. 6. 9. 1.1 8.21725 6 57 70. 6. 7. 5.5 0.8 11.521725 6 58 70. 7. 8. 3.6 0.7 16.21725 6 59 80. 1. 2. 140. 15. 2.121725 6 60 80. 2. 3. 80. 8. 1.921725 6 61 80. 3. 4. 37. 4. 2.821725 6 62 80. 4. 5. 22. 2.3 3.921725 6 63 80. 5. 6. 12.2 1.4 5.821725 6 64 80. 6. 7. 7.8 1. 7.821725 6 65 80. 7. 8. 5.1 0.7 10.921725 6 66 90. 1. 2. 160. 16. 1.621725 6 67 90. 2. 3. 74. 8. 1.821725 6 68 90. 3. 4. 35. 4. 2.721725 6 69 90. 4. 5. 18. 2. 4.21725 6 70 90. 5. 6. 10.8 1.2 5.721725 6 71 90. 6. 7. 7.3 0.9 7.421725 6 72 90. 7. 8. 5. 0.7 9.821725 6 73 100. 1. 2. 153. 17. 2.21725 6 74 100. 2. 3. 74. 7. 2.121725 6 75 100. 3. 4. 35. 4. 3.121725 6 76 100. 4. 5. 19. 2. 4.421725 6 77 100. 5. 6. 11. 1.3 6.621725 6 78 100. 6. 7. 7. 0.9 8.821725 6 79 100. 7. 8. 4.4 0.7 12.521725 6 80 110. 1. 2. 160. 16. 1.721725 6 81 110. 2. 3. 73. 8. 2.21725 6 82 110. 3. 4. 33.4 3.5 2.921725 6 83 110. 4. 5. 17.7 2. 4.321725 6 84 110. 5. 6. 10.7 1.2 6.121725 6 85 110. 6. 7. 7. 0.9 8.221725 6 86 110. 7. 8. 3.6 0.6 13.921725 6 87 120. 1. 2. 173. 18. 1.921725 6 88 120. 2. 3. 81. 8. 2.121725 6 89 120. 3. 4. 39. 4. 3.21725 6 90 120. 4. 5. 20.5 2.3 4.721725 6 91 120. 5. 6. 10.3 1.3 7.321725 6 92 120. 6. 7. 6.8 0.9 9.721725 6 93 120. 7. 8. 4.3 0.7 14.21725 6 94 130. 1. 2. 183. 19. 1.921725 6 95 130. 2. 3. 81. 8. 2.121725 6 96 130. 3. 4. 38. 4. 3.221725 6 97 130. 4. 5. 20.5 2.3 4.721725 6 98 130. 5. 6. 11.4 1.4 7.21725 6 99 130. 6. 7. 6.7 1. 10.321725 6 100 130. 7. 8. 4.4 0.8 14.521725 6 101 140. 1. 2. 174. 18. 1.921725 6 102 140. 2. 3. 76. 8. 2.221725 6 103 140. 3. 4. 37. 4. 3.221725 6 104 140. 4. 5. 20. 2. 4.721725 6 105 140. 5. 6. 12.5 1.5 6.421725 6 106 140. 6. 7. 7.2 1. 9.521725 6 107 140. 7. 8. 4.6 0.7 13.721725 6 108 150. 1. 2. 172. 18. 2.321725 6 109 150. 2. 3. 74. 8. 2.721725 6 110 150. 3. 4. 35. 4. 3.921725 6 111 150. 4. 5. 20. 2.3 5.621725 6 112 150. 5. 6. 12.3 1.5 7.821725 6 113 150. 6. 7. 6.5 1. 12.721725 6 114 ENDDATA 99 0 21725 6 115 ENDSUBENT 114 0 21725 699999 SUBENT 21725007 20230130 231321725 7 1 BIB 5 10 21725 7 2 REACTION (92-U-238(N,X)0-NN-1,EM,SIG) 21725 7 3 ANALYSIS (INTAD,INTED) Integration of the data from 21725 7 4 Subent 006, by extrapolation to 0. energy 21725 7 5 and below 25 degr. and above 150. degr. 21725 7 6 CORRECTION Background. 21725 7 7 Neutron flux fluctuations. 21725 7 8 Elastic peak. 21725 7 9 STATUS (TABLE) Text on p.42 of CEA-R-3503,1968 21725 7 10 (DEP,21725006) Derived from Subent 006. 21725 7 11 HISTORY (20230130U) SD: BIB updated. 21725 7 12 ENDBIB 10 0 21725 7 13 NOCOMMON 0 0 21725 7 14 DATA 2 1 21725 7 15 DATA ERR-T 21725 7 16 B B 21725 7 17 8.47 0.72 21725 7 18 ENDDATA 3 0 21725 7 19 ENDSUBENT 18 0 21725 799999 ENDENTRY 7 0 2172599999999