ENTRY 20779 20170724 22622077900000001
SUBENT 20779001 20170724 22622077900100001
BIB 13 50 2077900100002
TITLE Absolute neutron fission cross sections of 235U, 238U, 2077900100003
and 239Pu at 13.9 and 14.6 MeV 2077900100004
AUTHOR (M.Cance, G.Grenier, D.Gimat, D.Parisot) 2077900100005
INSTITUTE (2FR BRC) 2077900100006
REFERENCE (J,NSE,68,197,1978) 2077900100007
(C,76ANL,,237,1976) Same 235U,238U(n,f) data 2077900100008
(C,75KIEV,5,363,1976) 14.6 MeV 235,238U data in table 2077900100009
(J,ANS,22,664,1975) Prelim. 235,238U data in table 2077900100010
FACILITY (VDG,2FR BRC) 550 keV Van de Graaff accelerator 2077900100011
INC-SOURCE (D-T) 210 keV deuterons (10 uA) of TiT (650 ug/cm2 2077900100012
thick) on a Ta backing (0.02 cm thick) 2077900100013
METHOD (ASSOP) 2077900100014
(TOF) to determine background due to alpha activity of 2077900100015
the deposit and due to fissions induced by unwanted 2077900100016
neutrons 2077900100017
(PHD) 2077900100018
PART-DET (N,A,FF) 2077900100019
DETECTOR (FISCH) Double 4-pi ionization chamber 2077900100020
(SOLST) To detect associated alpha at 70 deg 2077900100021
(En=13.9 MeV) or 125 deg (En=14.6 MeV) 2077900100022
(SCIN) Plastic scintillator (1.5 cm diam, 2.0 cm thick)2077900100023
served as a neutron monitor to count neutron-alpha 2077900100024
coincidences 2077900100025
CORRECTION Corrected for 2077900100026
- background 2077900100027
- ionization chamber efficiency 2077900100028
- extrapolation to zero pulse height (1.3%-2.3%)2077900100029
- loss of fissions (0.7%-0.9%)2077900100030
- neutron attenuation in target backing (1%-1.8%)2077900100031
- neutron attenuation in front face of fission chamber2077900100032
(1.5%)2077900100033
- fissions due to other isotopes (1%-3%)2077900100034
COMMENT By compiler (2017-07-24): 2077900100035
Table III of Nucl.Sci.Eng.68(1978)197 does not give 2077900100036
information on the energy dependence of the partial 2077900100037
uncertainties. The compiler kept only those expected 2077900100038
as constants of the neutron energy. 2077900100039
STATUS (TABLE) Table IV of Nucl.Sci.Eng.68(1978)197 2077900100040
HISTORY (19780320R) Special attached form with numerical 2077900100041
values from Grenier 2077900100042
(19781102C) 2077900100043
(19781213E) 2077900100044
(20071126A) Date is corrected 2077900100045
(20071127A) MISC heading determined. Error structure 2077900100046
given. DATA-ERR to ERR-T changed. Common value of 2077900100047
EN-ERR moved to SAN 001. SUBENTs cross reference 2077900100048
established 2077900100049
(20110223U) SD: in code METHOD keyword HE-AC deleted. 2077900100050
(20170724A) On. ERR-ANALYS moved to data subentries. 2077900100051
Major revision in 002-006. 2077900100052
ENDBIB 50 0 2077900100053
NOCOMMON 0 0 2077900100054
ENDSUBENT 53 0 2077900199999
SUBENT 20779002 20170724 22622077900200001
BIB 4 20 2077900200002
REACTION (92-U-235(N,F),,SIG) 2077900200003
SAMPLE Uranium acetate (60 mm in diam., 103.5 ug/cm2 thick) 2077900200004
electrosprayed on 20 ug/cm2 vyns foil metallized by 2077900200005
Al (20 ug/cm2 thick) 2077900200006
(92-U-235,ENR=0.9825) 2077900200007
(92-U-234,ENR=0.0146) 2077900200008
(92-U-236,ENR=0.0009) 2077900200009
(92-U-238,ENR=0.0020) 2077900200010
ERR-ANALYS (ERR-T) Quadrature sum of the following uncertainties: 2077900200011
- Statistics including background subtraction 2077900200012
- Extrapolation to zero pulse height 2077900200013
(0.6% for irradiation with 238U, 2077900200014
0.23% for irradiation with 239Pu) 2077900200015
(ERR-2) Loss of fissions (0.19%) 2077900200016
(ERR-3) Number of atoms per cm2 (1.4%) 2077900200017
(ERR-4) Neutron attenuation in target backing (0.36%) 2077900200018
(ERR-5) Neutron attenuation in front face of (0.3%) 2077900200019
fission chamber 2077900200020
(ERR-6) Fissions due to other isotopes (0.2%) 2077900200021
HISTORY (20170724A) On. ERR-ANALYS added. ERR-1, ERR-S deleted.2077900200022
ENDBIB 20 0 2077900200023
COMMON 5 3 2077900200024
ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2077900200025
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2077900200026
0.19 1.4 0.36 0.3 0.2 2077900200027
ENDCOMMON 3 0 2077900200028
DATA 4 2 2077900200029
EN EN-ERR DATA ERR-T 2077900200030
MEV MEV B B 2077900200031
13.9 0.13 2.062 0.039 2077900200032
14.6 0.13 2.063 0.039 2077900200033
ENDDATA 4 0 2077900200034
ENDSUBENT 33 0 2077900299999
SUBENT 20779003 20170724 22622077900300001
BIB 4 18 2077900300002
REACTION (92-U-238(N,F),,SIG) 2077900300003
SAMPLE Uranium acetate 60 mm in diam., 75.8 ug/cm2 thick) 2077900300004
electrosprayed on 20 ug/cm2 vyns foil metallized by 2077900300005
Al (20 ug/cm2 thick) 2077900300006
(92-U-238,ENR=0.9805) 2077900300007
(92-U-234,ENR=0.0192) 2077900300008
(92-U-235,ENR=0.0003) 2077900300009
(92-U-236,ENR=0.0000) 2077900300010
ERR-ANALYS (ERR-T) Quadrature sum of the following uncertainties: 2077900300011
- Statistics including background subtraction 2077900300012
(ERR-1) Extrapolation to zero pulse height (0.7%) 2077900300013
(ERR-2) Loss of fissions (0.17%) 2077900300014
(ERR-3) Number of atoms per cm2 (1.35%) 2077900300015
(ERR-4) Neutron attenuation in target backing (0.36%) 2077900300016
(ERR-5) Neutron attenuation in front face of (0.3%) 2077900300017
fission chamber 2077900300018
(ERR-6) Fissions due to other isotopes (0.4%) 2077900300019
HISTORY (20170724A) On. ERR-ANALYS added. ERR-S deleted. 2077900300020
ENDBIB 18 0 2077900300021
COMMON 6 3 2077900300022
ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2077900300023
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2077900300024
0.7 0.17 1.35 0.36 0.3 0.4 2077900300025
ENDCOMMON 3 0 2077900300026
DATA 4 2 2077900300027
EN EN-ERR DATA ERR-T 2077900300028
MEV MEV B B 2077900300029
13.9 0.13 1.143 0.025 2077900300030
14.6 0.13 1.149 0.025 2077900300031
ENDDATA 4 0 2077900300032
ENDSUBENT 31 0 2077900399999
SUBENT 20779004 20170724 22622077900400001
BIB 5 7 2077900400002
REACTION ((92-U-238(N,F),,SIG,,,DERIV)/ 2077900400003
(92-U-235(N,F),,SIG,,,DERIV)) 2077900400004
ANALYSIS Calculated from absolute measurements 2077900400005
ERR-ANALYS (DATA-ERR) Total uncertainty 2077900400006
STATUS (DEP,20779002) 235U(n,f) cross section 2077900400007
(DEP,20779003) 238U(n,f) cross section 2077900400008
HISTORY (20170724A) On. Parial uncertainties deleted. 2077900400009
ENDBIB 7 0 2077900400010
NOCOMMON 0 0 2077900400011
DATA 4 2 2077900400012
EN EN-ERR DATA DATA-ERR 2077900400013
MEV MEV NO-DIM NO-DIM 2077900400014
13.9 0.13 0.554 0.016 2077900400015
14.6 0.13 0.557 0.017 2077900400016
ENDDATA 4 0 2077900400017
ENDSUBENT 16 0 2077900499999
SUBENT 20779005 20170724 22622077900500001
BIB 4 17 2077900500002
REACTION (94-PU-239(N,F),,SIG) 2077900500003
SAMPLE Pu acetate (40 mm diam., 68 ug/cm2 thick) 2077900500004
electrosprayed on a vyns foil 2077900500005
(94-PU-239,ENR=0.9914) 2077900500006
(94-PU-238,ENR=0.000046) 2077900500007
(94-PU-240,ENR=0.00855) 2077900500008
(94-PU-242,ENR=0.0000038) 2077900500009
ERR-ANALYS (ERR-T) Quadrature sum of the following uncertainties: 2077900500010
- Statistics including background subtraction 2077900500011
(ERR-1) Extrapolation to zero pulse height (0.3%)2077900500012
(ERR-2) Loss of fissions (0.15%)2077900500013
(ERR-3) Number of atoms per cm2 (1.36%)2077900500014
(ERR-4) Neutron attenuation in target backing (0.36%)2077900500015
(ERR-5) Neutron attenuation in front face of 2077900500016
fission chamber (0.3%)2077900500017
(ERR-6) Fissions due to other isotopes (0.17%)2077900500018
HISTORY (20170724A) On. ERR-ANALYS added. ERR-S deleted. 2077900500019
ENDBIB 17 0 2077900500020
COMMON 6 3 2077900500021
ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2077900500022
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2077900500023
0.3 0.15 1.36 0.36 0.3 0.17 2077900500024
ENDCOMMON 3 0 2077900500025
DATA 4 2 2077900500026
EN EN-ERR DATA ERR-T 2077900500027
MEV MEV B B 2077900500028
13.9 0.13 2.321 0.058 2077900500029
14.6 0.13 2.290 0.052 2077900500030
ENDDATA 4 0 2077900500031
ENDSUBENT 30 0 2077900599999
SUBENT 20779006 20170724 22622077900600001
BIB 5 7 2077900600002
REACTION ((94-PU-239(N,F),,SIG,,,DERIV)/ 2077900600003
(92-U-235(N,F),,SIG,,,DERIV)) 2077900600004
ANALYSIS Calculated from absolute measurements 2077900600005
ERR-ANALYS (DATA-ERR) Total uncertainty 2077900600006
STATUS (DEP,20779002) 235U(n,f) cross section 2077900600007
(DEP,20779005) 238U(n,f) cross section 2077900600008
HISTORY (20170724A) On. Parial uncertainties deleted. 2077900600009
ENDBIB 7 0 2077900600010
NOCOMMON 0 0 2077900600011
DATA 4 2 2077900600012
EN EN-ERR DATA DATA-ERR 2077900600013
MEV MEV NO-DIM NO-DIM 2077900600014
13.9 0.13 1.125 0.035 2077900600015
14.6 0.13 1.110 0.033 2077900600016
ENDDATA 4 0 2077900600017
ENDSUBENT 16 0 2077900699999
ENDENTRY 6 0 2077999999999