ENTRY 11120 20170914 1112000000001
SUBENT 11120001 20170914 20180124 1112000100001
BIB 9 18 1112000100002
TITLE Nonelastic neutron cross section measurements on Li6, 1112000100003
Li7, U235, U238, and Pu239 at 8.1, 11.9, and 14.1 MeV 1112000100004
AUTHOR (M.H.MacGregor,R.Booth,W.P.Ball) 1112000100005
REFERENCE (J,PR,130,1471,1963) 1112000100006
#doi:10.1103/PhysRev.130.1471 1112000100007
REL-REF (M,11226001,M.H.MacGregor+,J,PR,108,726,1957) Sphere 1112000100008
transmission technique. 1112000100009
INSTITUTE (1USALRL) 1112000100010
FACILITY (CCW,1USALRL) Cockcroft-Walton accelerator. 1112000100011
INC-SOURCE (D-T) The D(d,n)He3 reaction, with a gas target, was 1112000100012
used to produce neutrons over a range from 9.7 to 14.5 1112000100013
MeV. 1112000100014
METHOD (SHELT) Spherical shell transmission. 1112000100015
HISTORY (19760628T) Translated from SCISRS 1112000100016
(19800814A) Converted to reaction formalism 1112000100017
(20170914A) BP: Revised the whole entry by adding 1112000100018
metadata. Updated to new date formats,lower case. 1112000100019
Corrections according last EXFOR rules and Dict. 1112000100020
ENDBIB 18 0 1112000100021
NOCOMMON 0 0 1112000100022
ENDSUBENT 21 0 1112000199999
SUBENT 11120002 20170914 20180124 1112000200001
BIB 5 19 1112000200002
REACTION (3-LI-6(N,NON),,SIG) 1112000200003
SAMPLE (3-LI-6,ENR=0.9442) The Li6 was 94.42% Li6 by 1112000200004
weight. 1112000200005
ERR-ANALYS (DATA-ERR) The quoted errors at 8 and 11 MeV in Table 1112000200006
I represent an educated guess as to probable error 1112000200007
limits. 1112000200008
CORRECTION Corrections were applied to the data for elastic 1112000200009
energy loss, multiple scattering, finite detector 1112000200010
size, variation of the beam energy and intensity with 1112000200011
angle, finite source-detector spacing, and the effect 1112000200012
of the 15-mil Armco iron container. At 14 MeV, 1112000200013
information on the lithium angular distribution is 1112000200014
available. At 8 MeV, the angular distribution was 1112000200015
estimated from other light-element angular 1112000200016
distributions. The 11 -MeV correction factors were 1112000200017
obtained by interpolation. Due to the lack of 1112000200018
knowledge about the angular distribution, the Anal 1112000200019
cross sections at 8 and 11 MeV are not very accurate. 1112000200020
STATUS (TABLE) Table I, page 1471. 1112000200021
ENDBIB 19 0 1112000200022
NOCOMMON 0 0 1112000200023
DATA 3 3 1112000200024
EN DATA DATA-ERR 1112000200025
MEV B B 1112000200026
8.1 3.8E-01 1.0E-01 1112000200027
1.19E+01 4.9E-01 1.0E-01 1112000200028
1.42E+01 5.2E-01 5.E-02 1112000200029
ENDDATA 5 0 1112000200030
ENDSUBENT 29 0 1112000299999
SUBENT 11120003 20170914 20180124 1112000300001
BIB 7 24 1112000300002
REACTION (3-LI-7(N,NON),,SIG) 1112000300003
SAMPLE (3-LI-7,ENR=0.985) The Li7 was 98.05% Li7 by weight. 1112000300004
ERR-ANALYS (DATA-ERR) The quoted errors at 8 and 11 MeV in Table 1112000300005
I represent an educated guess as to probable error 1112000300006
limits. 1112000300007
COMMENT Data corrected in priv.comm.,1964. 1112000300008
CORRECTION Corrections were applied to the data for elastic 1112000300009
energy loss, multiple scattering, finite detector 1112000300010
size, variation of the beam energy and intensity with 1112000300011
angle, finite source-detector spacing, and the effect 1112000300012
of the 15-mil Armco iron container. At 14 MeV, 1112000300013
information on the lithium angular distribution is 1112000300014
available. At 8 MeV, the angular distribution was 1112000300015
estimated from other light-element angular 1112000300016
distributions. The 11 -MeV correction factors were 1112000300017
obtained by interpolation. Due to the lack of 1112000300018
knowledge about the angular distribution, the Anal 1112000300019
cross sections at 8 and 11 MeV are not very accurate. 1112000300020
The Li7 cross section reported here is lower than 1112000300021
that of Li6 because inelastic scattering to the 1112000300022
0.477-MeV level in the case of Li7 could not be 1112000300023
separated from elastic scattering collisions. 1112000300024
STATUS (TABLE) priv.comm.,1964 1112000300025
HISTORY (19860106A) Data units corrected. 1112000300026
ENDBIB 24 0 1112000300027
NOCOMMON 0 0 1112000300028
DATA 3 3 1112000300029
EN DATA DATA-ERR 1112000300030
MEV MB MB 1112000300031
8.1 450. 200. 1112000300032
1.19E+01 430. 200. 1112000300033
1.42E+01 400. 50. 1112000300034
ENDDATA 5 0 1112000300035
ENDSUBENT 34 0 1112000399999
SUBENT 11120004 20170914 20180124 1112000400001
BIB 5 16 1112000400002
REACTION (92-U-235(N,NON),,SIG) 1112000400003
SAMPLE (92-U-235,ENR=0.935) 1112000400004
(92-U-238,ENR=0.065) 1112000400005
ERR-ANALYS (DATA-ERR) No details on sources of uncertainties. 1112000400006
CORRECTION Corrections were applied to the data for elastic 1112000400007
energy loss, multiple scattering, finite detector 1112000400008
size, variation of the beam energy and intensity with 1112000400009
angle, finite-source detector spacing, and fission 1112000400010
effects. The fission correction was determined by 1112000400011
first calibrating the detection efficiency for 1112000400012
fission neutrons at each detector bias by using the 1112000400013
spontaneous fissions from Pu240, and then measuring the1112000400014
induced fission rate by means of a detector bias set 1112000400015
above the initial neutron energy but below the upper 1112000400016
energy limit of the fission spectrum. 1112000400017
STATUS (TABLE) Table II, page 1471. 1112000400018
ENDBIB 16 0 1112000400019
NOCOMMON 0 0 1112000400020
DATA 3 3 1112000400021
EN DATA DATA-ERR 1112000400022
MEV B B 1112000400023
8.1 2.90 1.5E-01 1112000400024
1.19E+01 2.66 1.0E-01 1112000400025
1.41E+01 2.84 1.0E-01 1112000400026
ENDDATA 5 0 1112000400027
ENDSUBENT 26 0 1112000499999
SUBENT 11120005 20170914 20180124 1112000500001
BIB 5 15 1112000500002
REACTION (92-U-238(N,NON),,SIG) 1112000500003
SAMPLE (92-U-238,ENR=1.0) 1112000500004
ERR-ANALYS (DATA-ERR) No details on sources of uncertainties. 1112000500005
CORRECTION Corrections were applied to the data for elastic 1112000500006
energy loss, multiple scattering, finite detector 1112000500007
size, variation of the beam energy and intensity with 1112000500008
angle, finite-source detector spacing, and fission 1112000500009
effects. The fission correction was determined by 1112000500010
first calibrating the detection efficiency for 1112000500011
fission neutrons at each detector bias by using the 1112000500012
spontaneous fissions from Pu240, and then measuring the1112000500013
induced fission rate by means of a detector bias set 1112000500014
above the initial neutron energy but below the upper 1112000500015
energy limit of the fission spectrum. 1112000500016
STATUS (TABLE) Table II, page 1471. 1112000500017
ENDBIB 15 0 1112000500018
NOCOMMON 0 0 1112000500019
DATA 3 3 1112000500020
EN DATA DATA-ERR 1112000500021
MEV B B 1112000500022
8.1 2.95 1.5E-01 1112000500023
1.19E+01 2.83 1.0E-01 1112000500024
1.41E+01 2.95 1.0E-01 1112000500025
ENDDATA 5 0 1112000500026
ENDSUBENT 25 0 1112000599999
SUBENT 11120006 20170914 20180124 1112000600001
BIB 4 14 1112000600002
REACTION (94-PU-239(N,NON),,SIG) 1112000600003
ERR-ANALYS (DATA-ERR) No details on sources of uncertainties. 1112000600004
CORRECTION Corrections were applied to the data for elastic 1112000600005
energy loss, multiple scattering, finite detector 1112000600006
size, variation of the beam energy and intensity with 1112000600007
angle, finite-source detector spacing, and fission 1112000600008
effects. The fission correction was determined by 1112000600009
first calibrating the detection efficiency for 1112000600010
fission neutrons at each detector bias by using the 1112000600011
spontaneous fissions from Pu240, and then measuring the1112000600012
induced fission rate by means of a detector bias set 1112000600013
above the initial neutron energy but below the upper 1112000600014
energy limit of the fission spectrum. 1112000600015
STATUS (TABLE) Table II, page 1471. 1112000600016
ENDBIB 14 0 1112000600017
NOCOMMON 0 0 1112000600018
DATA 3 3 1112000600019
EN DATA DATA-ERR 1112000600020
MEV B B 1112000600021
8.1 3.20 2.0E-01 1112000600022
1.19E+01 2.84 1.2E-01 1112000600023
1.41E+01 2.69 2.0E-01 1112000600024
ENDDATA 5 0 1112000600025
ENDSUBENT 24 0 1112000699999
ENDENTRY 6 0 1112099999999