ENTRY 40958 20130219 41604095800000001 SUBENT 40958001 20130219 41604095800100001 BIB 15 39 4095800100002 INSTITUTE (4RUSRI) 4095800100003 REFERENCE (J,AE,64,(2),150,198802) 4095800100004 (J,SJA,64,(2),179,1988) Engl.transl. of J,E,64,(2),150 4095800100005 #doi:10.1007/BF01153734 4095800100006 AUTHOR (Yu.N.Trofimov) 4095800100007 TITLE U-236 neutron radiation capture cross-section 4095800100008 for En=0.3-2.2 MeV 4095800100009 FACILITY (VDG,4RUSRI) 4095800100010 INC-SOURCE (P-T) 4095800100011 METHOD (ACTIV) 4095800100012 DETECTOR (GELI) Ge(Li) detector of 38 cm**3 volume -to measure 4095800100013 energy and intensity of gammas. 4095800100014 Energy resolution 3.8 keV for Co-60 gamma-lines. 4095800100015 Spectrometer was calibrated by standard gamma-sources,4095800100016 additionally by Np-237-,Pa-233. Efficiency dependence4095800100017 was calibrated absolutely at 86.5, 312, 340, 415.8keV.4095800100018 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 4095800100019 MONIT-REF (,,R,STI/DOC/10-227,1983) 4095800100020 DECAY-DATA (92-U-237,6.752D,DG,208.,0.224) 4095800100021 HL=6.752+-0.002d. 4095800100022 REL-REF (R,,A.V.Bushuev+,J,YK,1982,(2),30,1982) 4095800100023 Reference for U-237 208-keV gamma line intensity. 4095800100024 (R,,C.Lederer+,B,LEDERER-7,,1978) 4095800100025 Reference for U-237 HL. 4095800100026 DECAY-MON (79-AU-198,2.6946D,DG,411.8,0.9556) 4095800100027 HL=2.6946+-0.0010 d. 0.9556 +- 0.0007. 4095800100028 CORRECTION Correction were made for the neutron scattering on the4095800100029 structural materials - 3 %, for the neutron flux non- 4095800100030 stability - up to 5 %, for the gamma-rays self-absor- 4095800100031 ption - 1-to-4 % . 4095800100032 HISTORY (19880729C) Compiled at the CJD 4095800100033 (20010315A) Date is corrected 4095800100034 (20110630A) M.M. J,SJA,64,(2),179,1988 was added. 4095800100035 Upper -> lower case correction. 4095800100036 TITLE was corrected. BIB information was added. 4095800100037 ERR-ANALYS was corrected according to now-day rules 4095800100038 and moved in Subent 002. 4095800100039 ERR-7 -> MONIT-ERR. 4095800100040 (20120219A) R,IAEA-227,1983 -> STI/DOC/10-227 . 4095800100041 ENDBIB 39 0 4095800100042 NOCOMMON 0 0 4095800100043 ENDSUBENT 42 0 4095800199999 SUBENT 40958002 20110630 41534095800200001 BIB 4 22 4095800200002 REACTION (92-U-236(N,G)92-U-237,,SIG) 4095800200003 SAMPLE Uranium oxide powder, U-234 content is .001 % , 4095800200004 U-235 content is 0.047 % ,U-236 content is 99.845+- 4095800200005 .005 % , U-238 content is 0.107+-.002 % . 4095800200006 Placed between polyethylene foils of .08 mm thickness 4095800200007 U samples of 9.61+-0.19, 6.20+-0.12 mg, Au - 45 mg. 4095800200008 ERR-ANALYS (ERR-1) Error due to the neutron scattering on struc- 4095800200009 tural materials 4095800200010 (ERR-2) Error caused by the neutron flux non-stability4095800200011 (ERR-3) Error due to the gamma-rays self-absorption 4095800200012 (ERR-4,1.,3.) Error of the gamma-activity measurement 4095800200013 (ERR-5,3.,4.) Error of the detector efficiency 4095800200014 (MONIT-ERR,6.,10.) Error of the monitor reaction 4095800200015 (ERR-8) Error of the geometry 4095800200016 (ERR-9) Error due to the isotopic purity of the 4095800200017 sample 4095800200018 (ERR-10) Error caused by the U-236 sample weighing 4095800200019 (ERR-11) Error caused by the Au-197 sample weighing 4095800200020 (ERR-T) Total error. 4095800200021 STATUS (TABLE) Table 2 of J,AE,64,(2),150,1988. 4095800200022 (COREL,41001042) Different samples. 4095800200023 (COREL,40975027) Different decay- data (intensity) 4095800200024 ENDBIB 22 0 4095800200025 COMMON 7 6 4095800200026 ERR-1 ERR-2 ERR-3 ERR-8 ERR-9 ERR-10 4095800200027 ERR-11 4095800200028 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4095800200029 PER-CENT 4095800200030 1. 0.2 0.5 1.5 .005 2.0 4095800200031 1.0 4095800200032 ENDCOMMON 6 0 4095800200033 DATA 5 11 4095800200034 EN EN-RSL DATA ERR-T MONIT 4095800200035 MEV MEV MB MB MB 4095800200036 .30 .14 127. 8. 206.5 4095800200037 .50 .13 118. 8. 134.6 4095800200038 .60 .13 105. 7. 116.2 4095800200039 .80 .13 125. 7. 90.8 4095800200040 1.00 .12 112. 7. 83. 4095800200041 1.20 .11 96. 7. 76. 4095800200042 1.30 .11 86. 9. 73.5 4095800200043 1.50 .10 62. 8. 71.5 4095800200044 1.85 .09 67. 8. 59.6 4095800200045 2.00 .08 57. 7. 54. 4095800200046 2.20 .08 62. 8. 46. 4095800200047 ENDDATA 13 0 4095800200048 ENDSUBENT 47 0 4095800299999 ENDENTRY 2 0 4095899999999