ENTRY 41597 20181224 41814159700000001 SUBENT 41597001 20181224 41814159700100001 BIB 14 79 4159700100002 TITLE Integral prompt neutron spectrum for fission of 235U 4159700100003 by thermal neutrons 4159700100004 AUTHOR (A.S.Vorobyev,O.A.Shcherbakov) 4159700100005 INSTITUTE (4RUSLIN) 4159700100006 REFERENCE (J,YK,,(1-2),37,2013) 4159700100007 For 2011-2012 years, published at 2013 . 4159700100008 (R,INDC(CCP)-0455,21,2014) 4159700100009 Engl.translation of YK,,(1-2),37,2013 4159700100010 REL-REF (I,41516001,A.S.Vorobyev+,J,NIM/A,598,795,2009) 4159700100011 Facility details. 4159700100012 In J,YK,,(1-2),37,2013 the corrections procedure was 4159700100013 changed and the data processing was improved. 4159700100014 FACILITY (REAC,4RUSLIN) Radial channel #7 of the research 4159700100015 reactor WWR-M equipped with a neutron mirror guide of 4159700100016 3m length. 4159700100017 INC-SOURCE (REAC) The collimated thermal neutron beam passed 4159700100018 through a 100-micron-thick Al window onto the target, 4159700100019 which was located in the center of the cylindrical 4159700100020 reaction chamber. The reaction chamber(350 mm diameter,4159700100021 walls manufactured from 2 mm duraluminum) was filled 4159700100022 with isobutane up to a pressure of 4-5 Torr. 4159700100023 INC-SPECT Neutrons average energy 0.0363 eV, neutron flux from 4159700100024 the neutron-guide outlet slit (3x40 mm2 in cross 4159700100025 section) was equal to approximately 2E+7 1/cm**2/sec . 4159700100026 SAMPLE The U-235 target as a spot of 15 mm diameter, 4159700100027 280 microg/cm**2 thickness on the self-supporting 4159700100028 70 microg/cm**2 thick Al(2)O(3) ( or Ti) backing. 4159700100029 Cf-252 layer with a diameter of 10 mm was made by 4159700100030 self-transfer in vacuum on a 0.18-mm-thick stainless 4159700100031 steel foil. 4159700100032 METHOD (TOF) Neutron energy and fission fragments velocity 4159700100033 were determined by TOF. 4159700100034 (PSD) Double discrimination by the pulse shape and 4159700100035 time-of-flight was used to separate the events produced4159700100036 by neutrons and gammas. 4159700100037 (COINC) FF-N, LF-HF, LF-HF-N. 4159700100038 Four cycles ( each of two weeks) of measurement were 4159700100039 performed. During each cycle, the angular and energy 4159700100040 distributions of the prompt fission neutrons were 4159700100041 measured in turn for the thermal-neutron-induced 4159700100042 fission of 235U and the spontaneous fission of 252Cf. 4159700100043 The 252Cf target was installed in the reaction chamber 4159700100044 at the same position as the 235U target. 4159700100045 DETECTOR (MWPC) - One MWPD as start detector of 3.5mm thickness,4159700100046 20x92 mm2 sensitive square, located at 3.5 mm from 4159700100047 fissile target. FF registration efficiency 97 %. 4159700100048 - 16 MWPD of 3 mm thickness, 72x38 mm2 square, 4159700100049 installed in two arcing formations (8 MWPCs in each 4159700100050 formation, diametrically opposite to each other) in 4159700100051 the reaction chamber at a distance of 140 mm from the 4159700100052 chamber axis were used to determine the velocities of 4159700100053 the fission fragments and their directions of motion. 4159700100054 (SCIN) Two scintillation detectors for neutron 4159700100055 registration - stilbene crystals of 50 mm diameter, 4159700100056 50mm high and 60 mm diameter, 40mm high combined with 4159700100057 Hamamatsu-R6091 phototubes, positioned with 90 deg 4159700100058 angle between their respective axis at distances 4159700100059 49.2+-0.3 cm and 47.2+-0.3 cm from target. 4159700100060 Neutron registration threshold 150-200 keV. 4159700100061 CORRECTION -For time uncertainties in the time-of-flight 4159700100062 measurements. 4159700100063 -For neutron detector background. 4159700100064 -For the fragment detector efficiency. 4159700100065 -For complementary fragment contribution. 4159700100066 -For derivation of a neutron energy spectrum from the 4159700100067 measured neutron TOF spectrum and correction for 4159700100068 relativistic effects. 4159700100069 -For angular and neutron-energy resolution of the 4159700100070 experimental set-up. 4159700100071 -Bin-width and normalization corrections. 4159700100072 -For neutron-detection efficiency and total prompt 4159700100073 fission neutron spectrum of 235U(n,f). 4159700100074 STATUS (APRVD) Approved by author O.Shcherbakov 01.04.2014 . 4159700100075 HISTORY (20140120C) M.M. 4159700100076 (20160605U) SD: Page numb. was added to INDC(CCP)-0455.4159700100077 Title update following INDC(CCP)-0455. 4159700100078 (20170710U) M.M. 4159700100079 J,YK,2011,(1-2),37,2013 -> J,YK,,(1-2),37,2013 4159700100080 (20181224U) Misprint was corrected in Subents 003,004 4159700100081 ENDBIB 79 0 4159700100082 NOCOMMON 0 0 4159700100083 ENDSUBENT 82 0 4159700199999 SUBENT 41597002 20140120 41634159700200001 BIB 4 25 4159700200002 REACTION ((92-U-235(N,F),PR,NU/DE)/ 4159700200003 (98-CF-252(0,F),PR,NU/DE)) 4159700200004 Ratio of prompt fission neutrons spectra. 4159700200005 MISC-COL (MISC1) Correction factor for angular resolution. 4159700200006 (MISC2) Correction factor for energy resolution. 4159700200007 (MISC3) Correction factor defined as ratio of integral 4159700200008 spectra U/Cf obtained by Simpson method angular 4159700200009 integration with angular bin of 1 degree. 4159700200010 (MISC4) Correction factor defined as ratio of integral 4159700200011 spectra U/Cf obtained by Simpson method angular 4159700200012 integration with angular bin of 18 degree. 4159700200013 (MISC5) Total correction factor. 4159700200014 ERR-ANALYS (ERR-T) Total uncertainty includes : 4159700200015 (ERR-S) Statistical uncertainty for U . 4159700200016 (ERR-1) Statistical uncertainty for Cf. 4159700200017 (ERR-2) Uncertainty due to background. 4159700200018 (ERR-3) Uncertainty due to correction using the 4159700200019 approximation by Maxwellian spectrum with temperature 4159700200020 T = 1.42 MeV for Cf and 1.314 MeV for U-235. 4159700200021 (ERR-4) Uncertainty due to ratio of detector length to 4159700200022 TOF base h/D. 4159700200023 STATUS (TABLE) Table 2 of J,YK,(2011-2012),(1-2),2013 - data 4159700200024 and uncertainties. 4159700200025 Values of corrections are given in Table 1 of 4159700200026 J,YK,(2011-2012),(1-2),2013 . 4159700200027 ENDBIB 25 0 4159700200028 COMMON 1 3 4159700200029 EN 4159700200030 EV 4159700200031 0.0363 4159700200032 ENDCOMMON 3 0 4159700200033 DATA 13 49 4159700200034 E DATA ERR-T ERR-S ERR-1 ERR-2 4159700200035 ERR-3 ERR-4 MISC1 MISC2 MISC3 MISC4 4159700200036 MISC5 4159700200037 MEV NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT 4159700200038 PER-CENT PER-CENT NO-DIM NO-DIM NO-DIM NO-DIM 4159700200039 NO-DIM 4159700200040 16.650 0.1577 46.9 36.7 14.2 23.1 4159700200041 2.7 37.6 1.120 0.976 0.980 1.073 4159700200042 1.150 4159700200043 13.290 0.2961 25.9 14.3 10.7 15.6 4159700200044 2.3 28.4 1.056 0.980 0.984 1.063 4159700200045 1.081 4159700200046 10.860 0.3880 16.7 6.8 7.6 5.9 4159700200047 1.9 22.1 1.019 0.982 0.985 1.052 4159700200048 1.036 4159700200049 9.043 0.4299 12.7 3.8 6.2 2.7 4159700200050 1.6 17.7 1.007 0.986 0.987 1.042 4159700200051 1.021 4159700200052 7.647 0.4778 9.8 3.1 4.1 1.5 4159700200053 1.3 14.3 0.998 0.986 0.989 1.034 4159700200054 1.006 4159700200055 6.552 0.5403 7.9 2.4 3.2 1.0 4159700200056 1.0 11.8 0.996 0.989 0.990 1.028 4159700200057 1.002 4159700200058 5.677 0.5651 6.7 1.6 3.1 0.7 4159700200059 0.9 9.8 0.996 0.991 0.990 1.023 4159700200060 1.000 4159700200061 4.967 0.5912 5.4 1.5 2.1 0.4 4159700200062 0.7 8.2 0.995 0.994 0.991 1.019 4159700200063 0.999 4159700200064 4.383 0.6169 4.6 1.3 1.9 0.3 4159700200065 0.6 6.9 0.994 0.996 0.992 1.016 4159700200066 0.998 4159700200067 3.896 0.6266 3.9 1.1 1.7 0.2 4159700200068 0.5 5.8 0.996 0.996 0.992 1.013 4159700200069 0.997 4159700200070 3.486 0.6449 3.3 1.0 1.4 0.2 4159700200071 0.4 4.9 0.995 0.997 0.993 1.011 4159700200072 0.996 4159700200073 3.137 0.6494 3.1 0.9 1.6 0.1 4159700200074 0.4 4.2 0.994 0.998 0.992 1.010 4159700200075 0.993 4159700200076 2.839 0.6437 2.6 0.8 1.5 0.1 4159700200077 0.3 3.5 0.995 0.999 0.991 1.008 4159700200078 0.993 4159700200079 2.581 0.6552 2.3 0.7 1.4 0.1 4159700200080 0.3 3.0 0.994 1.000 0.992 1.007 4159700200081 0.994 4159700200082 2.357 0.6784 2.2 0.7 1.5 0.1 4159700200083 0.2 2.5 0.995 1.000 0.992 1.006 4159700200084 0.994 4159700200085 2.161 0.6632 1.9 0.8 1.2 0.1 4159700200086 0.2 2.1 0.996 1.000 0.992 1.005 4159700200087 0.994 4159700200088 1.988 0.6782 1.8 0.8 1.3 0.1 4159700200089 0.2 1.7 0.997 1.000 0.994 1.005 4159700200090 0.996 4159700200091 1.835 0.6761 1.7 0.8 1.2 0.1 4159700200092 0.2 1.4 0.997 1.000 0.994 1.005 4159700200093 0.996 4159700200094 1.699 0.6744 1.5 0.7 1.1 0.1 4159700200095 0.2 1.1 0.998 1.000 0.996 1.004 4159700200096 0.998 4159700200097 1.578 0.6616 1.8 0.8 1.5 0.1 4159700200098 0.1 0.9 0.998 1.000 0.996 1.004 4159700200099 0.998 4159700200100 1.469 0.6646 1.7 0.8 1.5 0.1 4159700200101 0.1 0.7 0.998 1.000 0.997 1.003 4159700200102 0.998 4159700200103 1.372 0.6765 1.9 0.7 1.7 0.1 4159700200104 0.1 0.5 0.998 1.000 0.998 1.003 4159700200105 0.999 4159700200106 1.283 0.6735 1.4 0.9 1.0 0.1 4159700200107 0.1 0.3 0.999 1.000 0.998 1.002 4159700200108 0.999 4159700200109 1.203 0.6686 1.6 0.8 1.4 0.1 4159700200110 0.1 0.2 0.998 1.000 1.000 1.002 4159700200111 1.000 4159700200112 1.130 0.6817 1.4 0.9 1.1 0.1 4159700200113 0.1 0.1 0.999 1.000 0.999 1.002 4159700200114 1.000 4159700200115 1.064 0.6763 1.9 0.9 1.7 0.1 4159700200116 0.1 0.1 0.999 1.000 0.999 1.002 4159700200117 1.001 4159700200118 1.003 0.6746 2.1 0.9 1.9 0.1 4159700200119 0.1 0.1 0.999 1.000 1.000 1.002 4159700200120 1.001 4159700200121 0.948 0.6776 1.7 0.9 1.4 0.1 4159700200122 0.1 0.1 0.999 1.000 0.999 1.002 4159700200123 0.999 4159700200124 0.896 0.6668 2.4 1.1 2.1 0.1 4159700200125 0.1 0.1 1.000 1.000 0.998 1.002 4159700200126 1.000 4159700200127 0.849 0.6681 1.9 1.0 1.6 0.1 4159700200128 0.1 0.1 0.999 1.000 0.998 1.002 4159700200129 0.999 4159700200130 0.806 0.6648 2.4 1.1 2.1 0.1 4159700200131 0.1 0.1 0.999 1.000 0.999 1.001 4159700200132 0.999 4159700200133 0.766 0.6756 2.5 1.1 2.2 0.1 4159700200134 0.1 0.2 0.999 1.001 0.999 1.001 4159700200135 0.999 4159700200136 0.728 0.6717 2.1 1.3 1.7 0.1 4159700200137 0.1 0.3 0.999 1.000 0.998 1.001 4159700200138 0.998 4159700200139 0.694 0.6623 2.5 1.1 2.2 0.1 4159700200140 0.0 0.4 0.999 1.000 0.998 1.001 4159700200141 0.998 4159700200142 0.661 0.6720 2.6 1.3 2.2 0.1 4159700200143 0.0 0.6 0.999 1.000 0.998 1.001 4159700200144 0.998 4159700200145 0.631 0.6597 2.3 1.3 1.9 0.1 4159700200146 0.0 0.8 1.000 1.000 0.997 1.001 4159700200147 0.998 4159700200148 0.603 0.6660 2.8 1.5 2.3 0.1 4159700200149 0.0 1.0 0.999 1.000 0.998 1.001 4159700200150 0.998 4159700200151 0.577 0.6782 2.9 1.4 2.4 0.2 4159700200152 0.0 1.2 0.999 1.000 0.997 1.001 4159700200153 0.997 4159700200154 0.553 0.6602 3.0 1.5 2.5 0.2 4159700200155 0.0 1.5 0.999 1.000 0.998 1.001 4159700200156 0.998 4159700200157 0.530 0.6666 3.2 1.5 2.7 0.2 4159700200158 0.0 1.7 0.999 1.000 0.997 1.001 4159700200159 0.997 4159700200160 0.488 0.6853 2.2 1.0 1.5 0.2 4159700200161 0.0 2.3 0.999 1.000 0.997 1.001 4159700200162 0.997 4159700200163 0.434 0.6671 2.7 1.0 1.6 0.2 4159700200164 0.1 3.3 1.000 1.000 0.997 1.002 4159700200165 0.999 4159700200166 0.388 0.6411 3.5 1.1 2.2 0.2 4159700200167 0.0 4.4 0.999 1.000 0.998 1.001 4159700200168 0.998 4159700200169 0.349 0.7089 4.4 1.4 2.7 0.3 4159700200170 0.1 5.5 1.000 1.000 0.997 1.001 4159700200171 0.998 4159700200172 0.316 0.6603 4.7 1.5 2.1 0.3 4159700200173 0.0 6.7 1.000 1.000 0.998 1.001 4159700200174 0.999 4159700200175 0.287 0.6681 5.7 1.9 2.9 0.3 4159700200176 0.0 7.9 0.999 1.000 0.998 1.001 4159700200177 0.998 4159700200178 0.263 0.6328 6.8 2.2 3.7 0.3 4159700200179 0.0 9.0 0.999 1.000 0.998 1.001 4159700200180 0.998 4159700200181 0.241 0.6919 7.7 2.8 4.2 0.7 4159700200182 0.0 10.1 0.999 1.000 0.998 1.001 4159700200183 0.998 4159700200184 0.221 0.6824 9.7 3.6 5.9 2.9 4159700200185 0.0 11.3 0.998 1.000 0.999 1.001 4159700200186 0.998 4159700200187 ENDDATA 153 0 4159700200188 ENDSUBENT 187 0 4159700299999 SUBENT 41597003 20181224 41814159700300001 BIB 6 11 4159700300002 REACTION (92-U-235(N,F),PR,NU/DE) 4159700300003 Total prompt fission neutron spectrum. 4159700300004 MONITOR ((MONIT1)98-CF-252(0,F),PR,NU/DE,,NPD) 4159700300005 ((MONIT2)98-CF-252(0,F),PR,NU) 4159700300006 MONIT-REF (,,3,ENDF/B-VII.1,,2011) 4159700300007 ERR-ANALYS (ERR-T) Total uncertainty including monitor uncertainty4159700300008 and total uncertainty of U/Cf spectra ratio. 4159700300009 (MONIT1-ERR) Uncertainty of Cf spectrum. 4159700300010 STATUS (TABLE) Table 2 of J.Yad.Konst.,(1-2),37,2013. 4159700300011 (DEP,41597002) Spectra ratio. 4159700300012 HISTORY (20181224U) Misprint in STATUS (DEP,...) was corrected 4159700300013 ENDBIB 11 0 4159700300014 COMMON 2 3 4159700300015 EN MONIT2 4159700300016 EV PRT/FIS 4159700300017 0.0363 3.759 4159700300018 ENDCOMMON 3 0 4159700300019 DATA 5 49 4159700300020 E DATA ERR-T MONIT1 MONIT1-ERR 4159700300021 MEV PT/FIS/MEV PER-CENT 1/MEV PER-CENT 4159700300022 16.650 0.1074E-4 49.4 0.1812E-4 15.6 4159700300023 13.290 1.958 E-4 26.3 1.759 E-4 4.5 4159700300024 10.860 13.3 E-4 17.0 9.103 E-4 2.9 4159700300025 9.043 49.6 E-4 12.9 30.7 E-4 2.2 4159700300026 7.647 139.9 E-4 10.0 77.9 E-4 1.9 4159700300027 6.552 326.6 E-4 8.1 160.8 E-4 1.6 4159700300028 5.677 602.4 E-4 6.8 283.6 E-4 1.5 4159700300029 4.967 987.8 E-4 5.6 444.5 E-4 1.4 4159700300030 4.383 1484.2E-4 4.8 640.0 E-4 1.3 4159700300031 3.896 2023.6E-4 4.1 859.1 E-4 1.2 4159700300032 3.486 2647.1E-4 3.5 1092. E-4 1.2 4159700300033 3.137 3249.0E-4 3.3 1331. E-4 1.2 4159700300034 2.839 3784.3E-4 2.9 1564. E-4 1.2 4159700300035 2.581 4396.4E-4 2.6 1785. E-4 1.2 4159700300036 2.357 5084.7E-4 2.4 1994. E-4 1.1 4159700300037 2.161 5452.3E-4 2.1 2187. E-4 1.1 4159700300038 1.988 6028.9E-4 2.2 2365. E-4 1.2 4159700300039 1.835 6415.1E-4 2.0 2524. E-4 1.2 4159700300040 1.699 6770.6E-4 2.0 2671. E-4 1.3 4159700300041 1.578 6943.5E-4 2.1 2792. E-4 1.2 4159700300042 1.469 7245.3E-4 2.1 2900. E-4 1.2 4159700300043 1.372 7615.8E-4 2.2 2995. E-4 1.2 4159700300044 1.283 7784.4E-4 1.8 3075. E-4 1.2 4159700300045 1.203 7909.7E-4 2.0 3147. E-4 1.2 4159700300046 1.130 8197.6E-4 1.9 3199. E-4 1.2 4159700300047 1.064 8244.2E-4 2.3 3243. E-4 1.3 4159700300048 1.003 8325.0E-4 2.6 3283. E-4 1.6 4159700300049 0.948 8432.8E-4 2.4 3311. E-4 1.7 4159700300050 0.896 8354.2E-4 3.0 3333. E-4 1.8 4159700300051 0.849 8418.5E-4 2.6 3352. E-4 1.8 4159700300052 0.806 8396.8E-4 3.0 3360. E-4 1.8 4159700300053 0.766 8533.3E-4 3.1 3360. E-4 1.8 4159700300054 0.728 8483.7E-4 2.9 3360. E-4 1.9 4159700300055 0.694 8365.1E-4 3.1 3360. E-4 1.8 4159700300056 0.661 8469.8E-4 3.1 3353. E-4 1.7 4159700300057 0.631 8285.0E-4 2.8 3341. E-4 1.6 4159700300058 0.603 8335.0E-4 3.3 3329. E-4 1.7 4159700300059 0.577 8458.3E-4 3.4 3318. E-4 1.8 4159700300060 0.553 8184.7E-4 3.5 3298. E-4 1.8 4159700300061 0.530 8218.7E-4 3.7 3280. E-4 1.8 4159700300062 0.488 8318.2E-4 2.8 3229. E-4 1.7 4159700300063 0.434 7933.9E-4 3.2 3164. E-4 1.7 4159700300064 0.388 7423.1E-4 3.9 3076. E-4 1.7 4159700300065 0.349 7988.8E-4 4.7 2998. E-4 1.7 4159700300066 0.316 7249.8E-4 5.0 2921. E-4 1.7 4159700300067 0.287 7132.0E-4 6.0 2840. E-4 1.8 4159700300068 0.263 6553.5E-4 7.0 2755. E-4 1.8 4159700300069 0.241 6957.0E-4 8.0 2675. E-4 1.9 4159700300070 0.221 6664.2E-4 9.9 2598. E-4 2.1 4159700300071 ENDDATA 51 0 4159700300072 ENDSUBENT 71 0 4159700399999 SUBENT 41597004 20181224 41814159700400001 BIB 6 24 4159700400002 REACTION 1(92-U-235(N,F)0-NN-1,PR,KEM) 4159700400003 2(92-U-235(N,F)0-NN-1,PR,KE) 4159700400004 3(92-U-235(N,F),PR,NU) 4159700400005 Parameters of Maxwellian distribution 4159700400006 MISC-COL (MISC1) Normalization coefficient = 4159700400007 ratio of NU-U to NU-fit for Maxwellian distribution. 4159700400008 Watt distribution parameters: 4159700400009 (MISC2) temperature, 4159700400010 (MISC3) energy Ew, 4159700400011 (MISC4) average energy, 4159700400012 (MISC5) fission-neutron yield, 4159700400013 (MISC6) normalization coefficient for Watt 4159700400014 distribution, see MISC1 for definition. 4159700400015 ANALYSIS Fitting of measured spectrum by Maxwellian and Watt 4159700400016 distributions. 4159700400017 Watt distribution in form: 4159700400018 W(Tw,Ew,En)=NUfit*SQRT(PI*Ew*Tw)*EXP(-(Ew+En)/Tw)* 4159700400019 SINH(2*SQRT(Ew*En)/Tw) 4159700400020 Better fitting of experimental spectrum was found to 4159700400021 be done by Watt distribution. 4159700400022 ERR-ANALYS (DATA-ERR) Total uncertainty . 4159700400023 STATUS (TABLE) Table 3 of J.Yad.Konst.,(1-2),37,2013. 4159700400024 (DEP,41597003) Spectrum. 4159700400025 HISTORY (20181224U) Misprint in STATUS (DEP,...) was corrected 4159700400026 ENDBIB 24 0 4159700400027 COMMON 1 3 4159700400028 EN 4159700400029 EV 4159700400030 0.0363 4159700400031 ENDCOMMON 3 0 4159700400032 DATA 16 1 4159700400033 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 34159700400034 MISC1 MISC2 MISC2-ERR MISC3 MISC3-ERR MISC4 4159700400035 MISC4-ERR MISC5 MISC5-ERR MISC6 4159700400036 MEV MEV MEV MEV PRT/FIS PRT/FIS 4159700400037 NO-DIM MEV MEV MEV MEV MEV 4159700400038 MEV PRT/FIS PRT/FIS NO-DIM 4159700400039 1.390 0.009 2.089 0.014 2.509 0.010 4159700400040 0.965 0.954 0.033 0.592 0.041 2.023 4159700400041 0.012 2.440 0.014 0.992 4159700400042 ENDDATA 9 0 4159700400043 ENDSUBENT 42 0 4159700499999 ENDENTRY 4 0 4159799999999