ENTRY 40158 20220202 42044015800000001 SUBENT 40158001 20220202 42044015800100001 BIB 9 45 4015800100002 TITLE Channel effects in the energy dependence of the number 4015800100003 of prompt neutrons and the kinetic energy of fragments 4015800100004 in the fission of U235 and U233 by neutrons 4015800100005 AUTHOR (Yu.A.Blyumkina,I.I.Bondarenko,V.F.Kuznetsov, 4015800100006 V.G.Nesterov,V.N.Okolovitch,G.N.Smirenkin,L.N.Usachev) 4015800100007 REFERENCE (J,NP,52,648,1964) Issue 4. Tables and graphs are given4015800100008 , data superseded, 4015800100009 supersedes AE 15,is.1,p.64,1963 and ICD-1,p.259,1964 4015800100010 (J,AE,15,64,1963) Issue 1. Graphs are given, 4015800100011 data superseded . 4015800100012 (J,SJA,15,725,1964) English transl. AE 4015800100013 (J,EAF,15,196,1964) France transl. AE 4015800100014 (R,ICD-1,259,1964) Data superseded 4015800100015 (R,ANL-TRANS-168,56,1967) English transl. ICD-1 4015800100016 (R,INDSWG-64E,22,1964) English translation of ICD-1 4015800100017 (R,FEI-47,1966) Same as part of ICD-3,51, 4015800100018 same data . 4015800100019 (R,FEI-48,1966) Same as part of ICD-3,51, 4015800100020 same data . 4015800100021 (R,ICD-3,51,1966) Corrected data and graphs are 4015800100022 given . First author V.F.Kusnetsov . 4015800100023 (R,INDSWG-152E,51,1967) English transl. of ICD-3 4015800100024 (J,AE,22,401,1967) Issue 5. First author V.F.Kuznetsov.4015800100025 Subent 006 data Table and graphs. 4015800100026 (J,SJA,22,500,1967) English transl. AE 22,401 4015800100027 (R,YFI-4,19,1967) Similar text,same Table as AE 22,401.4015800100028 First author V.F.Kuznetsov. 4015800100029 (R,INDC-187E,26,1967) English transl. of YFI-4,19 4015800100030 (R,YFI-4,18,1967) Similar text,same Table as AE 22,401.4015800100031 First author V.F.Kuznetsov. 4015800100032 (R,INDC-187E,26,1967) English transl. of YFI-4,18 4015800100033 (C,66PARIS,2,75,1966) 4015800100034 =STI/PUB/140 4015800100035 INSTITUTE (4RUSFEI) 4015800100036 FACILITY (VDG,4RUSFEI) 4015800100037 INC-SOURCE (P-T) 4015800100038 SAMPLE Disks of 30 mm diameter, 3 mm thickness. 4015800100039 STATUS Data from publication 4015800100040 HISTORY (19730321C) 4015800100041 (19740220A) Subentries 40158001,004-007 corrected . 4015800100042 (19750210A) Corrections in Subentries 001 and 005 made.4015800100043 (20090422A) M.M. BIB information was added. 4015800100044 Free text was corrected to be human-readable. 4015800100045 Dates were corrected for 4-digits year. 4015800100046 (20220202A) Update for current rules and dictionaries. 4015800100047 ENDBIB 45 0 4015800100048 NOCOMMON 0 0 4015800100049 ENDSUBENT 48 0 4015800199999 SUBENT 40158002 20220202 42044015800200001 BIB 8 32 4015800200002 REACTION ((92-U-235(N,F),PR,NU)//(92-U-235(N,F),PR,NU)) 4015800200003 Relative to value at 0.39 MeV. 4015800200004 DETECTOR (SCIN) Scintillation threshold stilbene crystal 4015800200005 detector . 4015800200006 (FISCH) Monitor fission chamber . 4015800200007 PART-DET (N,FF) 4015800200008 CORRECTION For anisotropy of fission fragments, 4015800200009 For change of fission neutron spectrum with 4015800200010 excitation energy of fissile nucleus and 4015800200011 For multiplication of neutrons in the uranium disc. 4015800200012 Correction for deviation of the distribution of the 4015800200013 number of fission across the thickness of the disc 4015800200014 from the linear distribution was negligible small. 4015800200015 MISC-COL (MISC1) Value of correction for deviation of the 4015800200016 distribution of the number of fission across thickness4015800200017 of the sample disc from the linear distribution . 4015800200018 (MISC2) Value of correction for angular anisotropy of 4015800200019 fission fragments and fission neutrons. 4015800200020 Defined analytically. 4015800200021 (MISC3) Value of correction for contribution from 4015800200022 secondary processes. 4015800200023 ERR-ANALYS (DATA-ERR) The errors of measurements given are 4015800200024 mainly due to the spread of different runs of 4015800200025 measurements. Include the uncertainties of corrections.4015800200026 STATUS (TABLE) Data from ICD-3,p.51,1966, Table 2 . 4015800200027 INDSWG-152E,51,1967 - English transl. of ICD-3 4015800200028 HISTORY (19730321T) Previously DASTAR 00363 4015800200029 (20090422A) Misprint in DATA value was corrected. 4015800200030 REACTION was corrected : (92-U-235(N,F),PR,NU,,REL) ->4015800200031 ((92-U-235(N,F),PR,NU)//(92-U-235(N,F),PR,NU)). 4015800200032 EN-DN was added. EN -> EN-NM . ARB-UNITS -> NO-DIM . 4015800200033 MISC1, MISC2, MISC3 were added. 4015800200034 ENDBIB 32 0 4015800200035 COMMON 1 3 4015800200036 EN-DN 4015800200037 MEV 4015800200038 0.39 4015800200039 ENDCOMMON 3 0 4015800200040 DATA 6 6 4015800200041 EN-NM DATA DATA-ERR MISC1 MISC2 MISC3 4015800200042 MEV NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 4015800200043 0.08 0.979 0.008 1.0014 0.9941 1.0007 4015800200044 0.310 0.997 0.006 1.0002 0.9994 0.9996 4015800200045 0.550 0.980 0.006 0.9998 1.0010 1.0003 4015800200046 0.670 0.992 0.007 0.9996 1.0026 1.0004 4015800200047 0.780 0.992 0.007 0.9996 1.0034 1.0004 4015800200048 0.990 1.005 0.009 0.9995 1.0034 1.0005 4015800200049 ENDDATA 8 0 4015800200050 ENDSUBENT 49 0 4015800299999 SUBENT 40158003 20220202 42044015800300001 BIB 8 33 4015800300002 REACTION ((92-U-235(N,F),PR,NU)//(92-U-235(N,F),PR,NU)) 4015800300003 Relative to value at 0.40 MeV 4015800300004 DETECTOR (FISCH) Multi-grid thorium chamber, 4015800300005 Monitor fission chamber 4015800300006 PART-DET (N,FF) 4015800300007 CORRECTION Corrections For anisotropy of fission fragments, 4015800300008 For change of fission neutron spectrum with4015800300009 excitation energy of fissile nucleus, 4015800300010 For multiplication of neutrons in the 4015800300011 uranium disk and 4015800300012 For deviation of the distribution of the 4015800300013 number of fissions across the thickness of the disc 4015800300014 from the linear distribution were introduced . 4015800300015 MISC-COL (MISC1) Value of correction for deviation of the 4015800300016 distribution of the number of fission across thickness4015800300017 of the sample disc from the linear distribution . 4015800300018 (MISC2) Value of correction for angular anisotropy of 4015800300019 fission fragments and fission neutrons. 4015800300020 Defined by calculation method . 4015800300021 (MISC3) Value of correction for contribution from 4015800300022 secondary processes. 4015800300023 (MISC4) Value of correction for neutron registration 4015800300024 efficiency dependence across sample disk. 4015800300025 ERR-ANALYS (DATA-ERR) In data errors the corrections 4015800300026 introducing error was included. 4015800300027 STATUS (TABLE) Data from ICD-3,p.51,1966, Table 3 . 4015800300028 INDSWG-152E,51,1967 - English transl. of ICD-3 4015800300029 HISTORY (19730321T) Preliminary data from DASTAR 00919 4015800300030 (20090422A) REACTION was corrected : 4015800300031 (92-U-235(N,F),PR,NU,,REL) -> 4015800300032 ((92-U-235(N,F),PR,NU)//(92-U-235(N,F),PR,NU)). 4015800300033 EN-DN was added. EN -> EN-NM . ARB-UNITS -> NO-DIM . 4015800300034 MISC1, MISC2, MISC3, MISC4 were added. 4015800300035 ENDBIB 33 0 4015800300036 COMMON 1 3 4015800300037 EN-DN 4015800300038 MEV 4015800300039 0.40 4015800300040 ENDCOMMON 3 0 4015800300041 DATA 7 6 4015800300042 EN-NM DATA DATA-ERR MISC1 MISC2 MISC3 4015800300043 MISC4 4015800300044 MEV NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 4015800300045 NO-DIM 4015800300046 0.08 0.986 0.006 1.0014 0.9940 1.0007 4015800300047 1.0031 4015800300048 0.20 1.013 0.007 1.0008 0.9973 0.9988 4015800300049 1.0005 4015800300050 0.30 1.008 0.006 1.0002 0.9994 0.9996 4015800300051 1.0002 4015800300052 0.50 0.998 0.005 0.9998 1.0006 1.0002 4015800300053 0.9998 4015800300054 0.60 0.995 0.005 0.9997 1.0016 1.0004 4015800300055 0.9997 4015800300056 0.70 0.994 0.005 0.9996 1.0030 1.0004 4015800300057 0.9997 4015800300058 ENDDATA 16 0 4015800300059 ENDSUBENT 58 0 4015800399999 SUBENT 40158004 20220202 42044015800400001 BIB 8 32 4015800400002 REACTION ((92-U-233(N,F),PR,NU)//(92-U-233(N,F),PR,NU)) 4015800400003 Relative to value at 0.4 MeV . 4015800400004 DETECTOR (FISCH) Multi-grid thorium chamber, 4015800400005 monitor fission chamber 4015800400006 PART-DET (N,FF) 4015800400007 CORRECTION Corrections For anisotropy of fission fragments, 4015800400008 For change of fission neutron spectrum with4015800400009 excitation energy of fission nucleus, 4015800400010 For multiplication of neutrons in the 4015800400011 uranium disc and 4015800400012 For deviation of the distribution of the 4015800400013 number of fission across the thickness of the disc 4015800400014 from the linear distribution were introduced . 4015800400015 MISC-COL (MISC1) Value of correction for deviation of the 4015800400016 distribution of the number of fission across thickness4015800400017 of the sample disc from the linear distribution . 4015800400018 (MISC2) Value of correction for angular anisotropy of 4015800400019 fission fragments and fission neutrons. 4015800400020 Defined by calculation method . 4015800400021 (MISC3) Value of correction for contribution from 4015800400022 secondary processes. 4015800400023 (MISC4) Value of correction for neutron registration 4015800400024 efficiency dependence across sample disk. 4015800400025 ERR-ANALYS (DATA-ERR) Errors produced by corrections to the data 4015800400026 have been added . 4015800400027 STATUS (TABLE) Data from ICD-3,51,1966, Table 1. 4015800400028 INDSWG-152E,51,1967 - English transl. of ICD-3 4015800400029 HISTORY (20090422A) REACTION was corrected : 4015800400030 (92-U-235(N,F),PR,NU,,REL) -> 4015800400031 ((92-U-235(N,F),PR,NU)//(92-U-235(N,F),PR,NU)). 4015800400032 EN-DN was added. EN -> EN-NM . ARB-UNITS -> NO-DIM . 4015800400033 MISC1, MISC2, MISC3, MISC4 were added. 4015800400034 ENDBIB 32 0 4015800400035 COMMON 1 3 4015800400036 EN-DN 4015800400037 MEV 4015800400038 0.40 4015800400039 ENDCOMMON 3 0 4015800400040 DATA 7 6 4015800400041 EN-NM DATA DATA-ERR MISC1 MISC2 MISC3 4015800400042 MISC4 4015800400043 MEV NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 4015800400044 NO-DIM 4015800400045 0.08 1.011 0.007 1.0022 0.9968 0.9989 4015800400046 1.0039 4015800400047 0.20 1.002 0.008 1.0004 0.9980 1.0000 4015800400048 1.0003 4015800400049 0.30 0.992 0.005 1.0003 0.9997 1.00007 4015800400050 1.0002 4015800400051 0.50 1.004 0.005 0.9997 1.0005 0.9996 4015800400052 0.9998 4015800400053 0.60 1.012 0.005 0.9994 1.0005 0.9996 4015800400054 0.9997 4015800400055 0.70 1.022 0.006 0.9995 1.0004 0.9986 4015800400056 0.9996 4015800400057 ENDDATA 16 0 4015800400058 ENDSUBENT 57 0 4015800499999 SUBENT 40158005 20220202 42044015800500001 BIB 6 21 4015800500002 REACTION (92-U-233(N,F),,NU) 4015800500003 MONITOR (92-U-233(N,F),,NU) 4015800500004 At thermal energy. 4015800500005 Ratio of total NU-BAR at thermal energy to one at 0.40 4015800500006 MeV was determined by analysis of data on average 4015800500007 kinetic energy of fission fragments and was equal to 4015800500008 1.013+-0.010. 4015800500009 ASSUMED (ASSUM,92-U-233(N,F),DL,NU) 4015800500010 Average number of delayed neutrons was equal to 0.007. 4015800500011 STATUS (DEP,40158004) Dependent from 40158.004 data of ratio. 4015800500012 (TABLE) Data from ICD-3,p.51,196611, Table 4 . 4015800500013 INDSWG-152E,51,1967 - English transl. of ICD-3 4015800500014 (OUTDT) Normalization out-of-date. 4015800500015 Renormalization was done in 4015800500016 At.Energy,v.34,is.6,p.491,1973. 4015800500017 Data are given in Subent 40189004 . 4015800500018 (SPSDD,40189004) Superseded by new data renormalized by4015800500019 authors. 4015800500020 ERR-ANALYS (DATA-ERR) Uncertainty of NU-BAR at thermal energy 4015800500021 was not included in the final error. 4015800500022 HISTORY (20220202S) NO-DIM -> PRT/FIS 4015800500023 ENDBIB 21 0 4015800500024 COMMON 3 3 4015800500025 EN-NRM MONIT ASSUM 4015800500026 EV PRT/FIS PRT/FIS 4015800500027 2.5300E-02 2.494 0.007 4015800500028 ENDCOMMON 3 0 4015800500029 DATA 3 7 4015800500030 EN DATA DATA-ERR 4015800500031 MEV PRT/FIS PRT/FIS 4015800500032 0.08 2.489 0.030 4015800500033 0.20 2.467 0.031 4015800500034 0.30 2.442 0.027 4015800500035 0.40 2.462 0.025 4015800500036 0.50 2.472 0.027 4015800500037 0.60 2.491 0.028 4015800500038 0.70 2.516 0.029 4015800500039 ENDDATA 9 0 4015800500040 ENDSUBENT 39 0 4015800599999 SUBENT 40158006 20220202 42044015800600001 BIB 7 23 4015800600002 REACTION (92-U-235(N,F),,NU) 4015800600003 MONITOR (92-U-235(N,F),,NU) 4015800600004 At thermal energy. 4015800600005 Measured ratio of total NU-BAR at thermal energy to one4015800600006 at 0.40 MeV was equal to 0.975+-0.007. 4015800600007 ASSUMED (ASSUM,92-U-235(N,F),DL,NU) 4015800600008 Average number of delayed neutrons was equal to 0.016. 4015800600009 FLAG (1.) Measurements with scintillation threshold 4015800600010 stilbene crystal detector 4015800600011 (2.) Measurements with multi-grid thorium chamber4015800600012 STATUS (DEP,40158002) Measured ratio for Flag 1. 4015800600013 (DEP,40158003) Measured ratio for Flag 2. 4015800600014 (TABLE) Data from ICD-3,p.66,1966, Table 6 . 4015800600015 INDSWG-152E,51,1967 - English transl. of ICD-3. 4015800600016 Also Table of YFI-4,p.19,1967= INDC(CCP)*017 . 4015800600017 INDC-187E,26,1967- English transl. of YFI-4,18. 4015800600018 Table of At.Energy,v.22,is.5,p.401,1967 4015800600019 HISTORY (19730321T) Preliminary data from DASTAR 00918,00919, 4015800600020 00363 4015800600021 (20090422A) Data units were corrected: 4015800600022 NO-DIM -> PRT/FIS . 4015800600023 ERR-ANALYS (DATA-ERR) Uncertainty of NU-BAR at thermal energy 4015800600024 was not included in the final error. 4015800600025 ENDBIB 23 0 4015800600026 COMMON 3 3 4015800600027 EN-NRM MONIT ASSUM 4015800600028 EV PRT/FIS PRT/FIS 4015800600029 2.5300E-02 2.430 0.016 4015800600030 ENDCOMMON 3 0 4015800600031 DATA 4 13 4015800600032 EN DATA DATA-ERR FLAG 4015800600033 MEV PRT/FIS PRT/FIS NO-DIM 4015800600034 0.08 2.456 0.022 2. 4015800600035 0.08 2.439 0.024 1. 4015800600036 0.20 2.523 0.025 2. 4015800600037 0.30 2.511 0.023 2. 4015800600038 0.31 2.483 0.022 1. 4015800600039 0.40 2.491 0.017 2. 4015800600040 0.50 2.486 0.022 2. 4015800600041 0.55 2.441 0.022 1. 4015800600042 0.60 2.478 0.021 2. 4015800600043 0.67 2.471 0.022 1. 4015800600044 0.70 2.476 0.022 2. 4015800600045 0.78 2.471 0.025 1. 4015800600046 0.99 2.503 0.029 1. 4015800600047 ENDDATA 15 0 4015800600048 ENDSUBENT 47 0 4015800699999 SUBENT 40158007 20220202 42044015800700001 BIB 7 25 4015800700002 REACTION ((92-U-235(N,F),PRE,AKE,FF)// 4015800700003 (92-U-235(N,F),PRE,AKE,FF)) 4015800700004 Relative to average kinetic 4015800700005 energy of fragments in fission by neutrons with 4015800700006 thermal energy . 4015800700007 DETECTOR (IOCH) Grid ionization chamber 4015800700008 REL-REF (M,,V.N.Okolovich+,J,AE,12,461,1962) Issue 6. 4015800700009 Method of treatment of the relative average kinetic 4015800700010 energy measurements. 4015800700011 CORRECTION Corrections For motion of the center-of-mass of the 4015800700012 fragments in the fission by fast neutrons, 4015800700013 For different yields of prompt neutrons, 4015800700014 For different losses of the fragment energy 4015800700015 in the layer because of the angular anisotropy and 4015800700016 For ionization defect were introduced . 4015800700017 ERR-ANALYS (DATA-ERR) The errors given were calculated from the 4015800700018 spread of data values taking into account the error due4015800700019 to the introduction of corrections. 4015800700020 STATUS (TABLE) Nucl.Phys.,v.52,is.4,p.657,1964, Table 3. 4015800700021 HISTORY (20090422A) REACTION was corrected: 4015800700022 (92-U-235(N,F),,AKE,FF,REL) -> 4015800700023 ((92-U-235(N,F),,AKE,FF)//(92-U-235(N,F),,AKE,FF)) . 4015800700024 EN-DN was added . EN -> EN-NM . ARB-UNITS -> NO-DIM .4015800700025 (20220202A) Code PRE was added in REACTIONs. 4015800700026 REL-REF was added. 4015800700027 ENDBIB 25 0 4015800700028 COMMON 1 3 4015800700029 EN-DN 4015800700030 EV 4015800700031 0.0253 4015800700032 ENDCOMMON 3 0 4015800700033 DATA 4 11 4015800700034 EN-NM EN-ERR DATA DATA-ERR 4015800700035 MEV MEV NO-DIM NO-DIM 4015800700036 0.08 0.9977 0.0019 4015800700037 0.28 0.09 0.9967 0.0014 4015800700038 0.35 0.09 0.9957 0.0018 4015800700039 0.48 0.09 0.9995 0.0014 4015800700040 0.68 0.09 1.0010 0.0019 4015800700041 0.77 0.09 1.0020 0.0019 4015800700042 0.87 0.09 1.0004 0.0016 4015800700043 1.09 0.09 1.0003 0.0025 4015800700044 1.45 0.10 1.0010 0.0015 4015800700045 1.90 0.10 0.9998 0.0020 4015800700046 2.46 0.11 1.0006 0.0022 4015800700047 ENDDATA 13 0 4015800700048 ENDSUBENT 47 0 4015800799999 SUBENT 40158008 20220202 42044015800800001 BIB 7 25 4015800800002 REACTION ((92-U-233(N,F),PRE,AKE,FF)// 4015800800003 (92-U-233(N,F),PRE,AKE,FF)) 4015800800004 Relative to average 4015800800005 kinetic energy of fragments in fission by neutrons 4015800800006 with thermal energy . 4015800800007 DETECTOR (IOCH) Grid ionization chamber 4015800800008 REL-REF (M,,V.N.Okolovich+,J,AE,12,461,1962) Issue 6. 4015800800009 Method of treatment of the relative average kinetic 4015800800010 energy measurements. 4015800800011 CORRECTION Corrections For motion of the center-of-mass of the 4015800800012 fragments in the fission by fast neutrons, 4015800800013 For different yields of prompt neutrons, 4015800800014 For different losses of the fragment energy4015800800015 in the layer because of the angular anisotropy and 4015800800016 For ionization defect were introduced. 4015800800017 ERR-ANALYS (DATA-ERR) The errors given were calculated from 4015800800018 the spread of data values taking into account the error4015800800019 due to the introduction of corrections. 4015800800020 STATUS (TABLE) Nucl.Phys.,v.52,is.4,p.658,1964, Table 4 . 4015800800021 HISTORY (20090422A) REACTION was corrected: 4015800800022 (92-U-235(N,F),,AKE,FF,REL) -> 4015800800023 ((92-U-235(N,F),,AKE,FF)//(92-U-235(N,F),,AKE,FF)) . 4015800800024 EN-DN was added . EN -> EN-NM . ARB-UNITS -> NO-DIM .4015800800025 (20220202A) Code PRE was added in REACTIONs. 4015800800026 REL-REF was added. U-235 -> U-233 ( see title of Fig.6)4015800800027 ENDBIB 25 0 4015800800028 COMMON 1 3 4015800800029 EN-DN 4015800800030 EV 4015800800031 0.0253 4015800800032 ENDCOMMON 3 0 4015800800033 DATA 4 13 4015800800034 EN-NM EN-ERR DATA DATA-ERR 4015800800035 MEV MEV NO-DIM NO-DIM 4015800800036 0.30 0.09 1.0050 0.0015 4015800800037 0.40 0.09 1.0038 0.0015 4015800800038 0.50 0.09 1.0041 0.0023 4015800800039 0.60 0.09 1.0009 0.0010 4015800800040 0.76 0.09 1.0000 0.0013 4015800800041 0.95 0.09 1.0040 0.0021 4015800800042 1.09 0.09 1.0033 0.0017 4015800800043 1.28 0.09 1.0043 0.0015 4015800800044 1.53 0.10 1.0041 0.0012 4015800800045 1.71 0.10 1.0045 0.0013 4015800800046 1.92 0.10 1.0060 0.0023 4015800800047 2.16 0.11 1.0056 0.0022 4015800800048 4.7 0.7 1.0018 0.0015 4015800800049 ENDDATA 15 0 4015800800050 ENDSUBENT 49 0 4015800899999 ENDENTRY 8 0 4015899999999