ENTRY 40177 20150109 41724017700000001 SUBENT 40177001 20150109 41724017700100001 BIB 12 45 4017700100002 INSTITUTE (4RUSFEI) 4017700100003 REFERENCE (J,SJA,33,945,1972) Eng.trans.of AE,33,825,1972 4017700100004 (J,AE,33,825,197210) Table of data and graph are given 4017700100005 AUTHOR (Yu.G.Panitkin,V.A.Tolstikov) 4017700100006 TITLE U-238 radiative capture cross section for 5 to 20 MeV 4017700100007 neutrons. 4017700100008 FACILITY (VDG) Two van de Graaff accelerators with a maximum 4017700100009 of energy 2.5 MeV and 5 MeV respectively 4017700100010 INC-SOURCE (D-D) Deuteron-deuterium reaction in neutron 4017700100011 energy range 5-7 MeV 4017700100012 (D-T) Deuteron-tritium reaction in the neutron energy 4017700100013 range 17-20 MeV 4017700100014 METHOD (ACTIV) Activation 4017700100015 DETECTOR (GELI) Germanium-lithium detector for gammas 4017700100016 (FISCH) Fission chamber for the neutron flux 4017700100017 measurements 4017700100018 DECAY-DATA (92-U-239,,DG,74.) 74.keV gamma peak was measured. 4017700100019 ANALYSIS After subtraction of background, the integral under 4017700100020 74 keV peak corresponds to induced activity of U-238. 4017700100021 CORRECTION Correction for: 4017700100022 * background of scattered neutrons(1-2%), 4017700100023 * neutrons inelastic scattering on construction 4017700100024 materials (10-12% for the sample and 2% for the 4017700100025 fission chamber), 4017700100026 * neutrons emitting from the target's backing(10-80% 4017700100027 for U-238 and 2-25% for the fission chamber) and 4017700100028 * admixture of the other fissile nuclei(4%) were 4017700100029 taken into account for the first region of the 4017700100030 measurements for the second one were induced the 4017700100031 corrections for background of neutrons(2%), 4017700100032 * inelastic scattering (10%) and 4017700100033 * neutrons emitting from the target backing (10-80% 4017700100034 for U-238 and 2-20% for Al foil) 4017700100035 HISTORY (19731122C) Compiled at the centre 4017700100036 (19750210A) Corrections in data-section of Subentry 0024017700100037 (19870608A) Subent 40177003 inserted containing 4017700100038 renormalized set of data for sigma(n,gamma) U-238 4017700100039 (20010314U) Dates and BIB-information corrected 4017700100040 (20021225A) Corrected at CJD 4017700100041 (20021225U) Last checking has been done. 4017700100042 (20150109A) SD: Ref. on Engl.transl. of AE added. 4017700100043 ERR-T -> DATA-ERR in Subent 2. Cosmetic corrections. 4017700100044 (20151103A) M.M. Article was checked, BIB information 4017700100045 was updated in TITLE,MONITOR,ANALYSIS 4017700100046 DECAY-DATA was added. 4017700100047 ENDBIB 45 0 4017700100048 NOCOMMON 0 0 4017700100049 ENDSUBENT 48 0 4017700199999 SUBENT 40177002 20150109 41724017700200001 BIB 7 32 4017700200002 REACTION (92-U-238(N,G)92-U-239,,SIG) 4017700200003 MONITOR ((MONIT1)92-U-238(N,G)92-U-239,,SIG) Normaliz. capture 4017700200004 cross-section at 24.4 KeV are taken from Nucl.Sci.and 4017700200005 Eng.,33,24,1968 4017700200006 ((MONIT2)92-U-235(N,F),,SIG) For neutron flux 4017700200007 measurement fission cross section of U-235 are taken 4017700200008 from W.Hart, Paper UK-10,UK-USSR Seminar, June, 1968 4017700200009 As flux monitor at 4-7 MeV energy range. 4017700200010 ((MONIT3)13-AL-27(N,P)12-MG-27,,SIG) For neutron 4017700200011 flux measurement n-p cross-sections are taken from 4017700200012 G.Calvi et al, Nucl.Phys,39,621,1962 and 4017700200013 G.Mani et al, Nucl.Phys.,19,535,1960 4017700200014 As flux monitor at 17-20 MeV energy range. 4017700200015 MONIT-REF ((MONIT1),H.Menlove+,J,NSE,33,24,1968) 4017700200016 ((MONIT2),W.Hart+,W,HART,1968) 4017700200017 ((MONIT3),G.Calvi+,J,NP,39,621,1962) 4017700200018 SAMPLE Powder of the oxide of U-238,before the activity 4017700200019 measurement the sample was purified from fission 4017700200020 fragments 4017700200021 STATUS (TABLE) .Tbl. 1 from AE,33,(4),825,1972 4017700200022 ERR-ANALYS (EN-ERR) The Error was conditioned by accelerator 4017700200023 beam attenuation and dependence of neutrons energy 4017700200024 upon the angle of incidence 4017700200025 (DATA-ERR) Mean square error of the experiment 4017700200026 for the first part of the experiment all errors of the 4017700200027 corrections except that in fission cross section of 4017700200028 U-235 and capture cross section of U-238 were taken 4017700200029 into account, for the second part the errors of (n,p) 4017700200030 cross section for Al were introduced besides that 4017700200031 HISTORY (20010314U) MONITOR keyword inserted 4017700200032 (20021225A) BIB-info specified 4017700200033 (20021225U) Last checking has been done. 4017700200034 ENDBIB 32 0 4017700200035 COMMON 2 3 4017700200036 EN-NRM MONIT1 4017700200037 KEV MB 4017700200038 24.4 516. 4017700200039 ENDCOMMON 3 0 4017700200040 DATA 7 7 4017700200041 EN EN-ERR DATA DATA-ERR MONIT2 MONIT3 4017700200042 MONIT3-ERR 4017700200043 MEV MEV MB MB B MB 4017700200044 MB 4017700200045 5.0 0.115 8.3 1. 1.09 4017700200046 4017700200047 6.0 0.136 6.8 0.9 1.11 4017700200048 4017700200049 7.0 0.16 5.8 1.1 1.59 4017700200050 4017700200051 17.0 0.26 3.7 1.3 50.4017700200052 10. 4017700200053 18.0 0.235 3.3 1.2 40.4017700200054 8. 4017700200055 19.0 0.25 2.9 1.4 40.4017700200056 8. 4017700200057 20.0 0.285 3.36 1.9 25.4017700200058 5. 4017700200059 ENDDATA 18 0 4017700200060 ENDSUBENT 59 0 4017700299999 SUBENT 40177003 20150109 41724017700300001 BIB 5 17 4017700300002 REACTION (92-U-238(N,G)92-U-239,,SIG) 4017700300003 MONITOR ((MONIT4)92-U-235(N,F),,SIG) 4017700300004 ERR-ANALYS (ERR-1) Error of the cross-section energy dependence 4017700300005 (ERR-S) Statistical error 4017700300006 (ERR-T) Total error 4017700300007 STATUS (TABLE) Re-normalized data from author 4017700300008 (APRVD) Tolstikov, 1987-06 4017700300009 (COREL,40121002) /* Data contained in articles */ 4017700300010 (COREL,40177002) /* 1. C,70Helsinki,Vol.2,51,1970 */ 4017700300011 (COREL,40431002) /* 2. C,70Helsinki,Vol.2,57,1970 */ 4017700300012 /* 3. J,AE,Vol.33,782, 1972 */ 4017700300013 /* 4. J,AE,Vol.33,825, 1972 */ 4017700300014 /* are renormalized by Tolstikov in 1987 */ 4017700300015 HISTORY (19870608C) Compiled at the Center - CJD 4017700300016 Renormalized Set of data for Sigma(n,gamma) U-238 4017700300017 (20021225A) Corrected at CJD. BIB-info added 4017700300018 (20021225U) Last checking has been done. 4017700300019 ENDBIB 17 0 4017700300020 NOCOMMON 0 0 4017700300021 DATA 8 36 4017700300022 EN EN-RSL-FW DATA ERR-S ERR-1 ERR-T 4017700300023 MONIT4 MONIT4-ERR 4017700300024 KEV KEV MB PER-CENT PER-CENT PER-CENT 4017700300025 B PER-CENT 4017700300026 24. 8. 478. 2.5 3. 5.9 4017700300027 2.21 2.3 4017700300028 30. 6. 454. 4.4 4017700300029 2.11 2.2 4017700300030 35. 8. 419. 3.1 3.5 6.1 4017700300031 2.04 2.4 4017700300032 45. 8.5 372. 2.2 2.7 5.8 4017700300033 1.89 2.4 4017700300034 55. 9. 364. 2.7 2.7 5.8 4017700300035 1.82 2.4 4017700300036 65. 10. 307. 2. 2.5 5.8 4017700300037 1.76 2.4 4017700300038 75. 10.5 279. 2.5 2.5 5.8 4017700300039 1.67 2.4 4017700300040 85. 11. 242. 2.1 3.1 6. 4017700300041 1.62 2.4 4017700300042 105. 11.5 211. 2.1 3.9 6.5 4017700300043 1.57 3.8 4017700300044 125. 12.5 187. 2.1 3.7 6.3 4017700300045 1.51 3.5 4017700300046 145. 13.5 168. 2.2 4.6 6.6 4017700300047 1.45 4.5 4017700300048 200. 18. 148. 2.2 2.7 5.8 4017700300049 1.36 2.4 4017700300050 250. 19. 136. 2.2 3.4 6.2 4017700300051 1.30 3.2 4017700300052 300. 19. 125. 2.2 3.5 6.3 4017700300053 1.26 3.3 4017700300054 400. 19.5 117.5 2.2 4. 6.5 4017700300055 1.21 3.7 4017700300056 500. 22. 114.5 2.2 4.3 6.7 4017700300057 1.16 4.1 4017700300058 600. 34. 113.5 2.2 4.2 6.7 4017700300059 1.14 4. 4017700300060 700. 35. 119.5 2.2 3.9 6.5 4017700300061 1.12 3.7 4017700300062 800. 36. 119.5 2.2 3.8 6.5 4017700300063 1.14 3.6 4017700300064 900. 36. 122.5 2.2 4.5 7. 4017700300065 1.18 4.3 4017700300066 1000. 39. 118.5 2.2 3.3 6.1 4017700300067 1.23 3. 4017700300068 1100. 41. 113.5 2.3 3.3 6.1 4017700300069 1.24 3. 4017700300070 1200. 43. 99. 2.4 4.4 6.8 4017700300071 1.25 4.1 4017700300072 1300. 45. 85.5 2.6 3.1 6. 4017700300073 1.24 2.4 4017700300074 1500. 49. 63. 2.7 3.1 6.1 4017700300075 1.24 2.6 4017700300076 1800. 54. 52. 2.9 3. 6. 4017700300077 1.28 2. 4017700300078 2000. 57. 44. 2.6 2.9 6. 4017700300079 1.28 2.2 4017700300080 2200. 61. 36.5 3.3 4. 6.3 4017700300081 1.28 2.4 4017700300082 2500. 67. 28.5 3.4 3.8 6.4 4017700300083 1.24 2.5 4017700300084 2800. 73. 23.5 3.8 4.2 6.6 4017700300085 1.22 2.5 4017700300086 3000. 78. 20. 3.6 3.9 6.5 4017700300087 1.21 2.3 4017700300088 3500. 94. 17.2 8.2 10. 4017700300089 1.18 2.9 4017700300090 4000. 110. 14.8 7.2 9.2 4017700300091 1.14 2.9 4017700300092 5000. 115. 9.3 12.2 13.5 4017700300093 1.09 3. 4017700300094 6000. 136. 7.8 13.3 14.3 4017700300095 1.14 2.9 4017700300096 7000. 160. 6.1 18.7 20. 4017700300097 1.52 5.3 4017700300098 ENDDATA 76 0 4017700300099 ENDSUBENT 98 0 4017700399999 ENDENTRY 3 0 4017799999999