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, data superseded, 4015800100009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data superseded . 4015800100012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(R,ICD-1,259,1964) Data superseded 4015800100015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