ENTRY 40650 20071122 41424065000000001 SUBENT 40650001 20071122 41424065000100001 BIB 13 29 4065000100002 INSTITUTE (4RUSFEI) 4065000100003 REFERENCE (J,AE,13,(4),366,1962) Main Reference. 4065000100004 (J,SJA,13,974,1963) Engl. translation of AE,13,366. 4065000100005 (R,ICD-4,339,1967) Data Table for SUBENTs .005, .006 . 4065000100006 AUTHOR (G.N.Smirenkin,B.G.Nesterov,I.I.Bondarenko) 4065000100007 TITLE U233,U235,Pu239 fission cross sections for 0.3-2.5 MeV 4065000100008 neutrons. 4065000100009 FACILITY (VDG) 4065000100010 INC-SOURCE (P-T) T(p,n)He-3 reaction on solid tritium target of 4065000100011 about 25 keV thickness. 4065000100012 DETECTOR (IOCH) Double ionization chamber for fission fragments 4065000100013 (BF3) Boron counter of 30 mm diameter and 70% B-10 in 4065000100014 paraffin block. For relative measurements of neutron 4065000100015 yields in direction of fissile layers. 4065000100016 REL-REF (R,,Vatset+,J,AE,7,(2),172,1959) Details of boron 4065000100017 counter construction. 4065000100018 SAMPLE Layers of about 1.5 mg/cm**2 thickness and 38mm 4065000100019 diameter. Uranium oxide enriched in U-235 to 92.1%. 4065000100020 Uranium U-233 oxide with admixtures of U-238 - 4.8%, 4065000100021 U-234 - 2.4%, U-235 - 0.7%. 4065000100022 Pu-239 with admixtures of Pu-240 - 1.8%. 4065000100023 CORRECTION For background of neutrons scattered in target and 4065000100024 walls of chamber - less 3.%. 4065000100025 STATUS (SCSRS,CURVE) 4065000100026 HISTORY (19831219T) Converted From ENTRY 80058 (SUB.002-.004) 4065000100027 (20071122A) M.M. BIB information was added. 4065000100028 SUBENTs .005, .006 were added. 4065000100029 ERR-ANALYS (ERR-S) Statistical uncertainty. 4065000100030 (ERR-1) Normalization uncertainty (5.-10%). Max. 4065000100031 ENDBIB 29 0 4065000100032 COMMON 2 3 4065000100033 ERR-1 ERR-S 4065000100034 PER-CENT PER-CENT 4065000100035 10. 1.0000E+00 4065000100036 ENDCOMMON 3 0 4065000100037 ENDSUBENT 36 0 4065000199999 SUBENT 40650002 20071122 41424065000200001 BIB 5 12 4065000200002 REACTION (92-U-233(N,F),,SIG) 4065000200003 MONITOR ((MONIT2)(92-U-233(N,F),,SIG)/(92-U-235(N,F),,SIG)) 4065000200004 MONIT-REF ((MONIT2)12356002,J.USE,C,58GENEVA,2,39,1959) 4065000200005 ANALYSIS At En=2.5MeV the U-233 fission cross-section was 4065000200006 defined by comparison of effective amounts of 4065000200007 substances in thermal neutron beam. 4065000200008 Resonance neutrons were excluded by cadmium difference4065000200009 measurement. 4065000200010 Cross-sections ratio at thermal energy from MONIT2 4065000200011 Reference, corrected for "Fermi" epithermal neutrons 4065000200012 contribution, was used for normalization(see MONIT2). 4065000200013 STATUS (DEP,40650005) 4065000200014 ENDBIB 12 0 4065000200015 COMMON 2 3 4065000200016 EN-NRM2 MONIT2 4065000200017 EV NO-DIM 4065000200018 0.025 0.935 4065000200019 ENDCOMMON 3 0 4065000200020 DATA 2 42 4065000200021 EN DATA 4065000200022 MEV B 4065000200023 2.8000E-01 2.2300E+00 4065000200024 3.5000E-01 2.2300E+00 4065000200025 4.5000E-01 2.1500E+00 4065000200026 4.7500E-01 2.0600E+00 4065000200027 5.2000E-01 1.9200E+00 4065000200028 5.7000E-01 1.8500E+00 4065000200029 6.1000E-01 1.7900E+00 4065000200030 6.7000E-01 1.8400E+00 4065000200031 7.4000E-01 1.8200E+00 4065000200032 7.7000E-01 1.8500E+00 4065000200033 8.1000E-01 1.8400E+00 4065000200034 8.4000E-01 1.8700E+00 4065000200035 8.7000E-01 1.8500E+00 4065000200036 9.2000E-01 1.8000E+00 4065000200037 9.5000E-01 1.7400E+00 4065000200038 1.0200E+00 1.7700E+00 4065000200039 1.0800E+00 1.7400E+00 4065000200040 1.1600E+00 1.7800E+00 4065000200041 1.2000E+00 1.7500E+00 4065000200042 1.2300E+00 1.7800E+00 4065000200043 1.2700E+00 1.8000E+00 4065000200044 1.3000E+00 1.7800E+00 4065000200045 1.3500E+00 1.8200E+00 4065000200046 1.3800E+00 1.8300E+00 4065000200047 1.4300E+00 1.8000E+00 4065000200048 1.4700E+00 1.8200E+00 4065000200049 1.5200E+00 1.7800E+00 4065000200050 1.5600E+00 1.8500E+00 4065000200051 1.5800E+00 1.8300E+00 4065000200052 1.6300E+00 1.8600E+00 4065000200053 1.7100E+00 1.9000E+00 4065000200054 1.7700E+00 1.9100E+00 4065000200055 1.8700E+00 1.8800E+00 4065000200056 1.9700E+00 1.9500E+00 4065000200057 2.0500E+00 2.0200E+00 4065000200058 2.1500E+00 1.9900E+00 4065000200059 2.2400E+00 1.9700E+00 4065000200060 2.3400E+00 1.9800E+00 4065000200061 2.4200E+00 1.9700E+00 4065000200062 2.5300E+00 1.9800E+00 4065000200063 2.5800E+00 2.0100E+00 4065000200064 2.6300E+00 1.9600E+00 4065000200065 ENDDATA 44 0 4065000200066 ENDSUBENT 65 0 4065000299999 SUBENT 40650003 20071122 41424065000300001 BIB 5 12 4065000300002 REACTION (94-PU-239(N,F),,SIG) 4065000300003 MONITOR ((MONIT3)(94-PU-239(N,F),,SIG)/(92-U-235(N,F),,SIG)) 4065000300004 MONIT-REF ((MONIT3)12356009,J.USE,C,58GENEVA,2,39,1959) 4065000300005 ANALYSIS At En=2.5MeV the Pu-239 fission cross-section was 4065000300006 defined by comparison of effective amounts of 4065000300007 substances in thermal neutron beam. 4065000300008 Resonance neutrons were excluded by cadmium difference4065000300009 measurement. 4065000300010 Cross-sections ratio at thermal energy from MONIT2 4065000300011 Reference, corrected for "Fermi" epithermal neutrons 4065000300012 contribution, was used for normalization(see MONIT3). 4065000300013 STATUS (DEP,40650006) 4065000300014 ENDBIB 12 0 4065000300015 COMMON 2 3 4065000300016 EN-NRM2 MONIT3 4065000300017 EV NO-DIM 4065000300018 0.025 1.50 4065000300019 ENDCOMMON 3 0 4065000300020 DATA 2 44 4065000300021 EN DATA 4065000300022 MEV B 4065000300023 2.9000E-01 1.6600E+00 4065000300024 3.5000E-01 1.6800E+00 4065000300025 4.0000E-01 1.6500E+00 4065000300026 4.8000E-01 1.6400E+00 4065000300027 5.2000E-01 1.6000E+00 4065000300028 5.5000E-01 1.5700E+00 4065000300029 5.8000E-01 1.5900E+00 4065000300030 6.0000E-01 1.5500E+00 4065000300031 6.2000E-01 1.5900E+00 4065000300032 6.8000E-01 1.6400E+00 4065000300033 7.3000E-01 1.6100E+00 4065000300034 7.8000E-01 1.6500E+00 4065000300035 8.2000E-01 1.7100E+00 4065000300036 8.5000E-01 1.6900E+00 4065000300037 8.9000E-01 1.6700E+00 4065000300038 9.2000E-01 1.6600E+00 4065000300039 9.6000E-01 1.6100E+00 4065000300040 9.9000E-01 1.6600E+00 4065000300041 1.0200E+00 1.6600E+00 4065000300042 1.0600E+00 1.6800E+00 4065000300043 1.0700E+00 1.6500E+00 4065000300044 1.1200E+00 1.6900E+00 4065000300045 1.1600E+00 1.7000E+00 4065000300046 1.1800E+00 1.7500E+00 4065000300047 1.2200E+00 1.7400E+00 4065000300048 1.2700E+00 1.7900E+00 4065000300049 1.3000E+00 1.8000E+00 4065000300050 1.3300E+00 1.8400E+00 4065000300051 1.3800E+00 1.8200E+00 4065000300052 1.4200E+00 1.8200E+00 4065000300053 1.4700E+00 1.8400E+00 4065000300054 1.5200E+00 1.8500E+00 4065000300055 1.5800E+00 1.9000E+00 4065000300056 1.6500E+00 1.8800E+00 4065000300057 1.6900E+00 1.9500E+00 4065000300058 1.7700E+00 1.9200E+00 4065000300059 1.8300E+00 1.9600E+00 4065000300060 1.9300E+00 1.9300E+00 4065000300061 2.0200E+00 1.9600E+00 4065000300062 2.1200E+00 1.9400E+00 4065000300063 2.2000E+00 1.9700E+00 4065000300064 2.3000E+00 1.9500E+00 4065000300065 2.3900E+00 1.9700E+00 4065000300066 2.5300E+00 1.9500E+00 4065000300067 ENDDATA 46 0 4065000300068 ENDSUBENT 67 0 4065000399999 SUBENT 40650004 20071122 41424065000400001 BIB 4 7 4065000400002 REACTION (92-U-235(N,F),,SIG) 4065000400003 MONITOR ((MONIT1)92-U-238(N,F),,SIG) 4065000400004 MONIT-REF ((MONIT1)12338008,R.LAMPHERE+,J,PR,104,1654,1956) 4065000400005 ANALYSIS Normalization of absolute cross-sections was carried 4065000400006 by comparison of number of fission counts in layers of 4065000400007 U-235 and natural uranium at fast and thermal neutrons,4065000400008 using the MONIT1 value at En=2.5 MeV. 4065000400009 ENDBIB 7 0 4065000400010 COMMON 2 3 4065000400011 EN-NRM MONIT1 4065000400012 MEV MB 4065000400013 2.5 5.8500E+02 4065000400014 ENDCOMMON 3 0 4065000400015 DATA 2 52 4065000400016 EN DATA 4065000400017 MEV B 4065000400018 3.5000E-01 1.3700E+00 4065000400019 4.2000E-01 1.3500E+00 4065000400020 4.5000E-01 1.2800E+00 4065000400021 5.1000E-01 1.2400E+00 4065000400022 5.8000E-01 1.1500E+00 4065000400023 6.4000E-01 1.1500E+00 4065000400024 7.0000E-01 1.1400E+00 4065000400025 7.5000E-01 1.1400E+00 4065000400026 8.0000E-01 1.1700E+00 4065000400027 8.2000E-01 1.1500E+00 4065000400028 8.5000E-01 1.1400E+00 4065000400029 8.8000E-01 1.1300E+00 4065000400030 9.0000E-01 1.1700E+00 4065000400031 9.5000E-01 1.1800E+00 4065000400032 1.0000E+00 1.2100E+00 4065000400033 1.0500E+00 1.2000E+00 4065000400034 1.0900E+00 1.2000E+00 4065000400035 1.1000E+00 1.1800E+00 4065000400036 1.1500E+00 1.2100E+00 4065000400037 1.2000E+00 1.2000E+00 4065000400038 1.2500E+00 1.2500E+00 4065000400039 1.2800E+00 1.2200E+00 4065000400040 1.3200E+00 1.2300E+00 4065000400041 1.3800E+00 1.2000E+00 4065000400042 1.4000E+00 1.2200E+00 4065000400043 1.4500E+00 1.2200E+00 4065000400044 1.5000E+00 1.2200E+00 4065000400045 1.5500E+00 1.2300E+00 4065000400046 1.6000E+00 1.2500E+00 4065000400047 1.6200E+00 1.2500E+00 4065000400048 1.6700E+00 1.2500E+00 4065000400049 1.7000E+00 1.2200E+00 4065000400050 1.7500E+00 1.2500E+00 4065000400051 1.8000E+00 1.2500E+00 4065000400052 1.8200E+00 1.2800E+00 4065000400053 1.8800E+00 1.3000E+00 4065000400054 1.9200E+00 1.3000E+00 4065000400055 1.9800E+00 1.2700E+00 4065000400056 2.0000E+00 1.2800E+00 4065000400057 2.0200E+00 1.2800E+00 4065000400058 2.0800E+00 1.2900E+00 4065000400059 2.1000E+00 1.2800E+00 4065000400060 2.1600E+00 1.3000E+00 4065000400061 2.2000E+00 1.3200E+00 4065000400062 2.2500E+00 1.3200E+00 4065000400063 2.3000E+00 1.3300E+00 4065000400064 2.3300E+00 1.3000E+00 4065000400065 2.4000E+00 1.2900E+00 4065000400066 2.4500E+00 1.3000E+00 4065000400067 2.5000E+00 1.3000E+00 4065000400068 2.5500E+00 1.3500E+00 4065000400069 2.6200E+00 1.3500E+00 4065000400070 ENDDATA 54 0 4065000400071 ENDSUBENT 70 0 4065000499999 SUBENT 40650005 20071122 41424065000500001 BIB 3 3 4065000500002 REACTION ((92-U-233(N,F),,SIG)/(92-U-235(N,F),,SIG)) 4065000500003 ERR-ANALYS (DATA-ERR) Uncertainty of measurement. 4065000500004 STATUS (TABLE) Table III of 3rd Reference. 4065000500005 ENDBIB 3 0 4065000500006 COMMON 1 3 4065000500007 DATA-ERR 4065000500008 PER-CENT 4065000500009 3. 4065000500010 ENDCOMMON 3 0 4065000500011 DATA 3 41 4065000500012 EN EN-ERR DATA 4065000500013 MEV MEV NO-DIM 4065000500014 0.350 0.030 1.740 4065000500015 0.410 0.024 1.695 4065000500016 0.465 0.023 1.682 4065000500017 0.525 0.022 1.657 4065000500018 0.585 0.022 1.670 4065000500019 0.640 0.021 1.657 4065000500020 0.695 0.021 1.674 4065000500021 0.740 0.020 1.677 4065000500022 0.770 0.020 1.704 4065000500023 0.800 0.020 1.704 4065000500024 0.835 0.020 1.741 4065000500025 0.870 0.020 1.728 4065000500026 0.910 0.020 1.652 4065000500027 0.950 0.020 1.605 4065000500028 0.990 0.020 1.546 4065000500029 1.020 0.020 1.571 4065000500030 1.095 0.034 1.595 4065000500031 1.160 0.032 1.595 4065000500032 1.205 0.032 1.560 4065000500033 1.245 0.032 1.547 4065000500034 1.280 0.030 1.577 4065000500035 1.315 0.030 1.555 4065000500036 1.350 0.030 1.577 4065000500037 1.395 0.029 1.590 4065000500038 1.435 0.029 1.563 4065000500039 1.475 0.028 1.607 4065000500040 1.515 0.028 1.568 4065000500041 1.555 0.027 1.573 4065000500042 1.595 0.027 1.573 4065000500043 1.635 0.027 1.583 4065000500044 1.720 0.026 1.604 4065000500045 1.800 0.025 1.595 4065000500046 1.890 0.024 1.537 4065000500047 1.980 0.024 1.606 4065000500048 2.065 0.023 1.619 4065000500049 2.160 0.023 1.580 4065000500050 2.250 0.022 1.576 4065000500051 2.340 0.021 1.603 4065000500052 2.435 0.021 1.595 4065000500053 2.530 0.020 1.595 4065000500054 2.625 0.020 1.575 4065000500055 ENDDATA 43 0 4065000500056 ENDSUBENT 55 0 4065000599999 SUBENT 40650006 20071122 41424065000600001 BIB 3 3 4065000600002 REACTION ((94-PU-239(N,F),,SIG)/(92-U-235(N,F),,SIG)) 4065000600003 ERR-ANALYS (DATA-ERR) Uncertainty of measurement. 4065000600004 STATUS (TABLE) Table III of 3rd Reference. 4065000600005 ENDBIB 3 0 4065000600006 COMMON 1 3 4065000600007 DATA-ERR 4065000600008 PER-CENT 4065000600009 3. 4065000600010 ENDCOMMON 3 0 4065000600011 DATA 3 40 4065000600012 EN EN-ERR DATA 4065000600013 MEV MEV NO-DIM 4065000600014 0.350 0.030 1.242 4065000600015 0.410 0.024 1.224 4065000600016 0.465 0.023 1.291 4065000600017 0.525 0.022 1.313 4065000600018 0.585 0.022 1.378 4065000600019 0.640 0.021 1.394 4065000600020 0.695 0.021 1.447 4065000600021 0.740 0.020 1.432 4065000600022 0.770 0.020 1.452 4065000600023 0.800 0.020 1.488 4065000600024 0.835 0.020 1.465 4065000600025 0.870 0.020 1.455 4065000600026 0.910 0.020 1.430 4065000600027 0.950 0.020 1.391 4065000600028 0.990 0.020 1.395 4065000600029 1.020 0.020 1.390 4065000600030 1.050 0.034 1.419 4065000600031 1.095 0.034 1.408 4065000600032 1.130 0.033 1.423 4065000600033 1.160 0.032 1.395 4065000600034 1.205 0.032 1.449 4065000600035 1.245 0.032 1.414 4065000600036 1.280 0.030 1.468 4065000600037 1.315 0.030 1.500 4065000600038 1.350 0.030 1.500 4065000600039 1.395 0.029 1.482 4065000600040 1.435 0.029 1.496 4065000600041 1.475 0.028 1.522 4065000600042 1.515 0.028 1.517 4065000600043 1.595 0.027 1.515 4065000600044 1.680 0.026 1.568 4065000600045 1.760 0.025 1.499 4065000600046 1.845 0.025 1.522 4065000600047 1.935 0.024 1.490 4065000600048 2.020 0.023 1.552 4065000600049 2.110 0.023 1.503 4065000600050 2.205 0.022 1.490 4065000600051 2.295 0.022 1.465 4065000600052 2.390 0.021 1.523 4065000600053 2.530 0.020 1.474 4065000600054 ENDDATA 42 0 4065000600055 ENDSUBENT 54 0 4065000699999 ENDENTRY 6 0 4065099999999