ENTRY 41480 20210611 41964148000000001 SUBENT 41480001 20210611 41964148000100001 BIB 11 36 4148000100002 TITLE Energy dependence of nuclear charge distribution in 4148000100003 neutron induced fission of Z-even nuclei 4148000100004 AUTHOR (V.A.Roshchenko, V.M.Piksaikin, S.G.Isaev, 4148000100005 A.A.Goverdovski) 4148000100006 INSTITUTE (4RUSFEI) 4148000100007 REFERENCE (J,PR/C,74,014607,2006) Main reference 4148000100008 (J,PNE,41,117,2002) Main features of exp. method 4148000100009 FACILITY (VDG,4RUSFEI) Electrostatic generator CG-2.5 4148000100010 INC-SOURCE (P-T) T(P,N)He-3 Reaction. Proton energies - 1.318, 4148000100011 1.550, 1.777, 1.974 MeV. Ion current on tritium target4148000100012 50. microA. 4148000100013 INC-SPECT Neutron flux of about 1.E+08 n/cm2/sec at sample. 4148000100014 Energy spectra of generated neutrons (determined by 4148000100015 Monte Carlo method)are presented on Fig.1 of Main Ref.4148000100016 Presented in article incident neutron energies are 4148000100017 maximal energies of incident neutron spectra (Fig.1), 4148000100018 correspondence: 4148000100019 EN-MAX EN 4148000100020 0.5 MeV 0.4 MeV 4148000100021 0.75 MeV 0.66 MeV 4148000100022 1.0 MeV 0.91 MeV 4148000100023 1.2 MeV 1.11 MeV 4148000100024 METHOD (ACTIV) Cyclic irradiation of fissionable sample. 4148000100025 Irradiation time - 180.06 and 300.06 sec. 4148000100026 DETECTOR (D4PI) 4148000100027 SAMPLE U-235 and Pu-239 samples in stainless steel capsules 4148000100028 with 0.3mm thick walls, enclosed in thin titanium cans.4148000100029 Each can contain four capsules. 4148000100030 Total uranium weight - up to 2.5 g, Isotopic content - 4148000100031 U-235 - 99%, U-238 - 1%. 4148000100032 Total plutonium weight - up to 3.6 g, isotopic content-4148000100033 Pu-239 - 95.96%, Pu-240 - 3.9%, Pu-241 - 0.14%. 4148000100034 HISTORY (20061130C) Compiled at CJD. M.M. 4148000100035 (20210611A) AUTHOR V.A.Roschenko -> V.A.Roshchenko. 4148000100036 Minor correction of free text. 4148000100037 Subent .004 was deleted - all data points are in .005. 4148000100038 ENDBIB 36 0 4148000100039 NOCOMMON 0 0 4148000100040 ENDSUBENT 39 0 4148000199999 SUBENT 41480002 20210611 41964148000200001 BIB 5 12 4148000200002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) 4148000200003 STATUS (TABLE) Table II of 4148000200004 Physical Review, Part C, v.74, p.014607,2006 4148000200005 ERR-ANALYS (DATA-ERR) Total error is root from sum of errors 4148000200006 squires. 4148000200007 Takes into account error of relative abundances, 4148000200008 error of delayed neutron yield, error of delayed 4148000200009 neutron emission probability. 4148000200010 COMMENT Of compiler. EN differs from energy, presented in 4148000200011 Table II. Changed according to authors' opinion. 4148000200012 See explanation in INC-SPEC lines (SUB.001). 4148000200013 HISTORY (20210611A) ERR-T -> DATA-ERR (no partial errors). 4148000200014 ENDBIB 12 0 4148000200015 NOCOMMON 0 0 4148000200016 DATA 5 33 4148000200017 EN ELEMENT MASS DATA DATA-ERR 4148000200018 MEV NO-DIM NO-DIM PC/FIS PC/FIS 4148000200019 2.53E-08 35. 87. 2.20 0.08 4148000200020 2.53E-08 35. 88. 2.42 0.09 4148000200021 2.53E-08 35. 89. 1.54 0.07 4148000200022 2.53E-08 35. 91. 0.22 0.03 4148000200023 2.53E-08 36. 93. 0.29 0.02 4148000200024 2.53E-08 37. 94. 2.01 0.09 4148000200025 2.53E-08 37. 95. 1.29 0.07 4148000200026 2.53E-08 53. 137. 3.39 0.13 4148000200027 2.53E-08 53. 138. 1.71 0.09 4148000200028 2.53E-08 53. 139. 0.67 0.04 4148000200029 2.53E-08 53. 140. 0.15 0.02 4148000200030 0.4 35. 87. 2.19 0.12 4148000200031 0.4 35. 88. 2.43 0.13 4148000200032 0.4 35. 89. 1.63 0.10 4148000200033 0.4 35. 91. 0.20 0.03 4148000200034 0.4 36. 93. 0.29 0.03 4148000200035 0.4 37. 94. 2.16 0.13 4148000200036 0.4 37. 95. 1.16 0.08 4148000200037 0.4 53. 137. 3.44 0.19 4148000200038 0.4 53. 138. 1.68 0.11 4148000200039 0.4 53. 139. 0.66 0.05 4148000200040 0.4 53. 140. 0.15 0.02 4148000200041 1.11 35. 87. 2.26 0.14 4148000200042 1.11 35. 88. 2.35 0.15 4148000200043 1.11 35. 89. 1.76 0.12 4148000200044 1.11 35. 91. 0.21 0.03 4148000200045 1.11 36. 93. 0.30 0.03 4148000200046 1.11 37. 94. 2.28 0.15 4148000200047 1.11 37. 95. 1.15 0.08 4148000200048 1.11 53. 137. 3.59 0.22 4148000200049 1.11 53. 138. 1.74 0.13 4148000200050 1.11 53. 139. 0.67 0.05 4148000200051 1.11 53. 140. 0.15 0.02 4148000200052 ENDDATA 35 0 4148000200053 ENDSUBENT 52 0 4148000299999 SUBENT 41480003 20210611 41964148000300001 BIB 5 12 4148000300002 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY) 4148000300003 STATUS (TABLE) Table II of 4148000300004 Physical Review, Part C, v.74, p.014607,2006 4148000300005 ERR-ANALYS (DATA-ERR) Total error is root from sum of errors 4148000300006 squires. 4148000300007 Takes into account error of relative abundances, 4148000300008 error of delayed neutron yield, error of delayed 4148000300009 neutron emission probability. 4148000300010 COMMENT Of compiler. EN differs from energy, presented in 4148000300011 Table II. Changed according to authors' opinion. 4148000300012 See explanation in INC-SPEC lines (SUB.001). 4148000300013 HISTORY (20210611A) ERR-T -> DATA-ERR (no partial errors). 4148000300014 ENDBIB 12 0 4148000300015 NOCOMMON 0 0 4148000300016 DATA 5 33 4148000300017 EN ELEMENT MASS DATA DATA-ERR 4148000300018 MEV NO-DIM NO-DIM PC/FIS PC/FIS 4148000300019 2.53E-08 35. 87. 0.75 0.05 4148000300020 2.53E-08 35. 88. 0.75 0.05 4148000300021 2.53E-08 35. 89. 0.34 0.03 4148000300022 2.53E-08 35. 91. 0.04 0.01 4148000300023 2.53E-08 36. 93. 0.15 0.01 4148000300024 2.53E-08 37. 94. 0.78 0.06 4148000300025 2.53E-08 37. 95. 0.36 0.03 4148000300026 2.53E-08 53. 137. 2.19 0.14 4148000300027 2.53E-08 53. 138. 0.99 0.07 4148000300028 2.53E-08 53. 139. 0.19 0.01 4148000300029 2.53E-08 53. 140. 0.027 0.004 4148000300030 0.4 35. 87. 0.76 0.05 4148000300031 0.4 35. 88. 0.71 0.05 4148000300032 0.4 35. 89. 0.35 0.03 4148000300033 0.4 35. 91. 0.04 0.01 4148000300034 0.4 36. 93. 0.15 0.01 4148000300035 0.4 37. 94. 0.79 0.06 4148000300036 0.4 37. 95. 0.41 0.03 4148000300037 0.4 53. 137. 2.17 0.15 4148000300038 0.4 53. 138. 1.01 0.07 4148000300039 0.4 53. 139. 0.19 0.02 4148000300040 0.4 53. 140. 0.027 0.004 4148000300041 1.11 35. 87. 0.83 0.05 4148000300042 1.11 35. 88. 0.74 0.05 4148000300043 1.11 35. 89. 0.38 0.03 4148000300044 1.11 35. 91. 0.04 0.01 4148000300045 1.11 36. 93. 0.16 0.01 4148000300046 1.11 37. 94. 0.86 0.06 4148000300047 1.11 37. 95. 0.38 0.03 4148000300048 1.11 53. 137. 2.11 0.14 4148000300049 1.11 53. 138. 1.02 0.07 4148000300050 1.11 53. 139. 0.20 0.02 4148000300051 1.11 53. 140. 0.030 0.004 4148000300052 ENDDATA 35 0 4148000300053 ENDSUBENT 52 0 4148000399999 NOSUBENT 41480004 20210611 41964148000400001 SUBENT 41480005 20210611 41964148000500001 BIB 4 11 4148000500002 REACTION (92-U-235(N,F)MASS,SEC,ZP) 4148000500003 ERR-ANALYS (DATA-ERR) Errors are not specified 4148000500004 STATUS (TABLE) Data received from authors 4148000500005 V.Roshchenko and V.Piksaikin 4148000500006 (DEP,41480002) Cumulative fission product yields 4148000500007 Table III of Physical Review,Part C,v.74,p.014607,20064148000500008 - data for 0.4 MeV; 4148000500009 EN differs from energy, presented in Table III; 4148000500010 changed according to authors' opinion, 4148000500011 see also explanation in INC-SPEC lines (SUB.001). 4148000500012 HISTORY (20210611A) SEC was added in SF5 4148000500013 ENDBIB 11 0 4148000500014 NOCOMMON 0 0 4148000500015 DATA 4 55 4148000500016 EN MASS DATA DATA-ERR 4148000500017 MEV NO-DIM NO-DIM NO-DIM 4148000500018 2.53E-08 87. 34.8945 0.0812 4148000500019 2.53E-08 88. 35.2442 0.0364 4148000500020 2.53E-08 89. 35.7432 0.023 4148000500021 2.53E-08 91. 36.4495 0.0385 4148000500022 2.53E-08 93. 37.3849 0.0206 4148000500023 2.53E-08 94. 37.7707 0.0224 4148000500024 2.53E-08 95. 37.9537 0.0205 4148000500025 2.53E-08 137. 53.4525 0.056 4148000500026 2.53E-08 138. 53.8549 0.0462 4148000500027 2.53E-08 139. 54.172 0.0358 4148000500028 2.53E-08 140. 54.5475 0.054 4148000500029 0.4 87. 34.8545 0.0148 4148000500030 0.4 88. 35.2076 0.060 4148000500031 0.4 89. 35.6742 0.0323 4148000500032 0.4 91. 36.4624 0.0398 4148000500033 0.4 93. 37.3858 0.0227 4148000500034 0.4 94. 37.7243 0.030 4148000500035 0.4 95. 37.9878 0.0241 4148000500036 0.4 137. 53.4421 0.0518 4148000500037 0.4 138. 53.8583 0.0568 4148000500038 0.4 139. 54.1693 0.0426 4148000500039 0.4 140. 54.5431 0.0554 4148000500040 0.66 87. 34.8385 0.167 4148000500041 0.66 88. 35.2108 0.068 4148000500042 0.66 89. 35.6411 0.0361 4148000500043 0.66 91. 36.4624 0.0398 4148000500044 0.66 93. 37.3806 0.0232 4148000500045 0.66 94. 37.7067 0.0329 4148000500046 0.66 95. 38.0069 0.0246 4148000500047 0.66 137. 53.4328 0.0926 4148000500048 0.66 138. 53.8464 0.0608 4148000500049 0.66 139. 54.1679 0.0442 4148000500050 0.66 140. 54.5401 0.0578 4148000500051 0.91 87. 34.8434 0.1614 4148000500052 0.91 88. 35.2162 0.0658 4148000500053 0.91 89. 35.6713 0.0351 4148000500054 0.91 91. 36.4576 0.0403 4148000500055 0.91 93. 37.3797 0.024 4148000500056 0.91 94. 37.7186 0.033 4148000500057 0.91 95. 37.9894 0.0258 4148000500058 0.91 137. 53.4243 0.0928 4148000500059 0.91 138. 53.8531 0.061 4148000500060 0.91 139. 54.166 0.0458 4148000500061 0.91 140. 54.5401 0.0578 4148000500062 1.11 87. 34.7674 0.2183 4148000500063 1.11 88. 35.2419 0.0637 4148000500064 1.11 89. 35.6344 0.0375 4148000500065 1.11 91. 36.4541 0.0398 4148000500066 1.11 93. 37.3772 0.0239 4148000500067 1.11 94. 37.6969 0.0342 4148000500068 1.11 95. 37.99 0.0264 4148000500069 1.11 137. 53.4083 0.0958 4148000500070 1.11 138. 53.8437 0.0632 4148000500071 1.11 139. 54.1642 0.0466 4148000500072 1.11 140. 54.5356 0.0568 4148000500073 ENDDATA 57 0 4148000500074 ENDSUBENT 73 0 4148000599999 SUBENT 41480006 20210611 41964148000600001 BIB 4 6 4148000600002 REACTION (94-PU-239(N,F)MASS,SEC,ZP) 4148000600003 STATUS (TABLE) Data received from authors 4148000600004 V.Roshchenko and V.Piksaikin 4148000600005 (DEP,41480003) Cumulative fission product yields 4148000600006 ERR-ANALYS (DATA-ERR) Errors are not specified 4148000600007 HISTORY (20210611A) SEC was added in SF5 4148000600008 ENDBIB 6 0 4148000600009 NOCOMMON 0 0 4148000600010 DATA 4 55 4148000600011 EN MASS DATA DATA-ERR 4148000600012 MEV NO-DIM NO-DIM NO-DIM 4148000600013 2.53E-08 87. 35.1007 0.085 4148000600014 2.53E-08 88. 35.4019 0.0537 4148000600015 2.53E-08 89. 35.9745 0.0305 4148000600016 2.53E-08 91. 36.7084 0.0398 4148000600017 2.53E-08 93. 37.4941 0.0232 4148000600018 2.53E-08 94. 38.017 0.0272 4148000600019 2.53E-08 95. 38.3191 0.0218 4148000600020 2.53E-08 137. 53.7554 0.0648 4148000600021 2.53E-08 138. 54.0601 0.0526 4148000600022 2.53E-08 139. 54.5367 0.038 4148000600023 2.53E-08 140. 54.9516 0.0584 4148000600024 0.4 87. 35.1398 0.0847 4148000600025 0.4 88. 35.4479 0.0412 4148000600026 0.4 89. 35.9698 0.0299 4148000600027 0.4 91. 36.7057 0.0389 4148000600028 0.4 93. 37.4895 0.0227 4148000600029 0.4 94. 38.0047 0.0277 4148000600030 0.4 95. 38.2682 0.0229 4148000600031 0.4 137. 53.7551 0.0686 4148000600032 0.4 138. 54.0528 0.0542 4148000600033 0.4 139. 54.5324 0.0404 4148000600034 0.4 140. 54.9504 0.058 4148000600035 0.66 87. 35.1107 0.0842 4148000600036 0.66 88. 35.4479 0.0684 4148000600037 0.66 89. 35.9641 0.0307 4148000600038 0.66 91. 36.7057 0.0389 4148000600039 0.66 93. 37.4861 0.0224 4148000600040 0.66 94. 38.0017 0.0275 4148000600041 0.66 95. 38.3048 0.0226 4148000600042 0.66 137. 53.7626 0.0652 4148000600043 0.66 138. 54.0562 0.053 4148000600044 0.66 139. 54.5258 0.0394 4148000600045 0.66 140. 54.9433 0.0564 4148000600046 0.91 87. 35.0733 0.0941 4148000600047 0.91 88. 35.3695 0.0574 4148000600048 0.91 89. 35.9641 0.0307 4148000600049 0.91 91. 36.6949 0.0373 4148000600050 0.91 93. 37.4776 0.0236 4148000600051 0.91 94. 38.0027 0.0276 4148000600052 0.91 95. 38.2782 0.0227 4148000600053 0.91 137. 53.8088 0.063 4148000600054 0.91 138. 54.0562 0.053 4148000600055 0.91 139. 54.5245 0.0394 4148000600056 0.91 140. 54.9433 0.0564 4148000600057 1.11 87. 35.0222 0.1056 4148000600058 1.11 88. 35.4122 0.0555 4148000600059 1.11 89. 35.9395 0.0308 4148000600060 1.11 91. 36.6949 0.0373 4148000600061 1.11 93. 37.4709 0.0231 4148000600062 1.11 94. 37.9715 0.0282 4148000600063 1.11 95. 38.2901 0.0226 4148000600064 1.11 137. 53.7709 0.067 4148000600065 1.11 138. 54.0484 0.0544 4148000600066 1.11 139. 54.5129 0.0404 4148000600067 1.11 140. 54.9297 0.0528 4148000600068 ENDDATA 57 0 4148000600069 ENDSUBENT 68 0 4148000699999 ENDENTRY 6 0 4148099999999