ENTRY 11120 20170914 14351112000000001 SUBENT 11120001 20170914 14351112000100001 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 14351112000200001 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 14351112000300001 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 14351112000400001 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 14351112000500001 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 14351112000600001 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