ENTRY 14743 20220208 149714743 0 1 SUBENT 14743001 20220208 149714743 1 1 BIB 8 14 14743 1 2 TITLE Inelastic collision and transport cross sections for 14743 1 3 some light elements 14743 1 4 AUTHOR (G.P.Arnold,E.T.Jurney,W.D.Schafer,E.O.Swickard, 14743 1 5 C.W.Zabel) 14743 1 6 REFERENCE (R,LA-1339,1951) Main reference. 14743 1 7 (J,PR,86,(H11),594,1952) Journal publication, minutes. 14743 1 8 Abstract only, no data. 14743 1 9 #doi:10.1103/PhysRev.86.579 14743 1 10 INSTITUTE (1USALAS) 14743 1 11 FACILITY (REAC,1USALAS) 14743 1 12 INC-SPECT Reactor spectrum from 1 to 7 MeV, maximum is around 2 14743 1 13 MeV. 14743 1 14 ERR-ANALYS (DATA-ERR) No details on sources of uncertainties. 14743 1 15 HISTORY (20220208C) BP 14743 1 16 ENDBIB 14 0 14743 1 17 COMMON 1 3 14743 1 18 EN-MEAN 14743 1 19 MEV 14743 1 20 2.0 14743 1 21 ENDCOMMON 3 0 14743 1 22 ENDSUBENT 21 0 14743 199999 SUBENT 14743002 20220208 149714743 2 1 BIB 4 4 14743 2 2 REACTION (4-BE-9(N,TOT),,SIG,,FST) 14743 2 3 DETECTOR (FISCH) 238U detector. 14743 2 4 METHOD (TRN) 14743 2 5 STATUS (TABLE) Table I, page 4 of report LA-1339,1951. 14743 2 6 ENDBIB 4 0 14743 2 7 NOCOMMON 0 0 14743 2 8 DATA 2 1 14743 2 9 DATA DATA-ERR 14743 2 10 B B 14743 2 11 2.18 0.052 14743 2 12 ENDDATA 3 0 14743 2 13 ENDSUBENT 12 0 14743 299999 SUBENT 14743003 20220208 149714743 3 1 BIB 4 4 14743 3 2 REACTION (6-C-0(N,TOT),,SIG,,FST) 14743 3 3 DETECTOR (FISCH) 238U detector. 14743 3 4 METHOD (TRN) 14743 3 5 STATUS (TABLE) Table I, page 4 of report LA-1339,1951. 14743 3 6 ENDBIB 4 0 14743 3 7 NOCOMMON 0 0 14743 3 8 DATA 2 1 14743 3 9 DATA DATA-ERR 14743 3 10 B B 14743 3 11 1.73 0.05 14743 3 12 ENDDATA 3 0 14743 3 13 ENDSUBENT 12 0 14743 399999 SUBENT 14743004 20220208 149714743 4 1 BIB 4 4 14743 4 2 REACTION (13-AL-27(N,TOT),,SIG,,FST) 14743 4 3 DETECTOR (FISCH) 238U detector. 14743 4 4 METHOD (TRN) 14743 4 5 STATUS (TABLE) Table I, page 4 of report LA-1339,1951. 14743 4 6 ENDBIB 4 0 14743 4 7 NOCOMMON 0 0 14743 4 8 DATA 2 1 14743 4 9 DATA DATA-ERR 14743 4 10 B B 14743 4 11 2.67 0.063 14743 4 12 ENDDATA 3 0 14743 4 13 ENDSUBENT 12 0 14743 499999 SUBENT 14743005 20220208 149714743 5 1 BIB 4 4 14743 5 2 REACTION (24-CR-0(N,TOT),,SIG,,FST) 14743 5 3 DETECTOR (FISCH) 238U detector. 14743 5 4 METHOD (TRN) 14743 5 5 STATUS (TABLE) Table I, page 4 of report LA-1339,1951. 14743 5 6 ENDBIB 4 0 14743 5 7 NOCOMMON 0 0 14743 5 8 DATA 2 1 14743 5 9 DATA DATA-ERR 14743 5 10 B B 14743 5 11 3.43 0.09 14743 5 12 ENDDATA 3 0 14743 5 13 ENDSUBENT 12 0 14743 599999 SUBENT 14743006 20220208 149714743 6 1 BIB 4 4 14743 6 2 REACTION (26-FE-0(N,TOT),,SIG,,FST) 14743 6 3 DETECTOR (FISCH) 238U detector. 14743 6 4 METHOD (TRN) 14743 6 5 STATUS (TABLE) Table I, page 4 of report LA-1339,1951. 14743 6 6 ENDBIB 4 0 14743 6 7 NOCOMMON 0 0 14743 6 8 DATA 2 1 14743 6 9 DATA DATA-ERR 14743 6 10 B B 14743 6 11 3.19 0.06 14743 6 12 ENDDATA 3 0 14743 6 13 ENDSUBENT 12 0 14743 699999 SUBENT 14743007 20220208 149714743 7 1 BIB 4 4 14743 7 2 REACTION (28-NI-0(N,TOT),,SIG,,FST) 14743 7 3 DETECTOR (FISCH) 238U detector. 14743 7 4 METHOD (TRN) 14743 7 5 STATUS (TABLE) Table I, page 4 of report LA-1339,1951. 14743 7 6 ENDBIB 4 0 14743 7 7 NOCOMMON 0 0 14743 7 8 DATA 2 1 14743 7 9 DATA DATA-ERR 14743 7 10 B B 14743 7 11 3.24 0.06 14743 7 12 ENDDATA 3 0 14743 7 13 ENDSUBENT 12 0 14743 799999 SUBENT 14743008 20220208 149714743 8 1 BIB 4 4 14743 8 2 REACTION (29-CU-0(N,TOT),,SIG,,FST) 14743 8 3 DETECTOR (FISCH) 238U detector. 14743 8 4 METHOD (TRN) 14743 8 5 STATUS (TABLE) Table I, page 4 of report LA-1339,1951. 14743 8 6 ENDBIB 4 0 14743 8 7 NOCOMMON 0 0 14743 8 8 DATA 2 1 14743 8 9 DATA DATA-ERR 14743 8 10 B B 14743 8 11 3.26 0.065 14743 8 12 ENDDATA 3 0 14743 8 13 ENDSUBENT 12 0 14743 899999 SUBENT 14743009 20220208 149714743 9 1 BIB 4 7 14743 9 2 REACTION (4-BE-9(N,EL)4-BE-9,,SIG,,FST) 14743 9 3 DETECTOR (FISCH) 238U detector. 14743 9 4 ANALYSIS The total elastic scattering cross section obtained 14743 9 5 separately by integrating a measured angular 14743 9 6 distribution of scattered neutrons over the entire 14743 9 7 sphere. 14743 9 8 STATUS (TABLE) Table I, page 4 of report LA-1339,1951. 14743 9 9 ENDBIB 7 0 14743 9 10 NOCOMMON 0 0 14743 9 11 DATA 2 1 14743 9 12 DATA DATA-ERR 14743 9 13 B B 14743 9 14 1.39 0.11 14743 9 15 ENDDATA 3 0 14743 9 16 ENDSUBENT 15 0 14743 999999 SUBENT 14743010 20220208 149714743 10 1 BIB 4 7 14743 10 2 REACTION (6-C-0(N,EL)6-C-0,,SIG,,FST) 14743 10 3 DETECTOR (FISCH) 238U detector. 14743 10 4 ANALYSIS The total elastic scattering cross section obtained 14743 10 5 separately by integrating a measured angular 14743 10 6 distribution of scattered neutrons over the entire 14743 10 7 sphere. 14743 10 8 STATUS (TABLE) Table I, page 4 of report LA-1339,1951. 14743 10 9 ENDBIB 7 0 14743 10 10 NOCOMMON 0 0 14743 10 11 DATA 2 1 14743 10 12 DATA DATA-ERR 14743 10 13 B B 14743 10 14 1.45 0.086 14743 10 15 ENDDATA 3 0 14743 10 16 ENDSUBENT 15 0 14743 1099999 SUBENT 14743011 20220208 149714743 11 1 BIB 5 10 14743 11 2 REACTION (13-AL-27(N,EL)13-AL-27,,SIG,,FST) 14743 11 3 DETECTOR (FISCH) 238U detector. 14743 11 4 ANALYSIS The total elastic scattering cross section obtained 14743 11 5 separately by integrating a measured angular 14743 11 6 distribution of scattered neutrons over the entire 14743 11 7 sphere. 14743 11 8 CORRECTION A correction for the loss in detection efficiency 14743 11 9 because of energy loss through elastic scattering was 14743 11 10 applied to the data for the cases of Al, Cr, and Fe. 14743 11 11 STATUS (TABLE) Table II, page 5 of report LA-1339,1951. 14743 11 12 ENDBIB 10 0 14743 11 13 NOCOMMON 0 0 14743 11 14 DATA 2 1 14743 11 15 DATA DATA-ERR 14743 11 16 B B 14743 11 17 1.64 0.21 14743 11 18 ENDDATA 3 0 14743 11 19 ENDSUBENT 18 0 14743 1199999 SUBENT 14743012 20220208 149714743 12 1 BIB 5 10 14743 12 2 REACTION (24-CR-0(N,EL)24-CR-0,,SIG,,FST) 14743 12 3 DETECTOR (FISCH) 238U detector. 14743 12 4 ANALYSIS The total elastic scattering cross section obtained 14743 12 5 separately by integrating a measured angular 14743 12 6 distribution of scattered neutrons over the entire 14743 12 7 sphere. 14743 12 8 CORRECTION A correction for the loss in detection efficiency 14743 12 9 because of energy loss through elastic scattering was 14743 12 10 applied to the data for the cases of Al, Cr, and Fe. 14743 12 11 STATUS (TABLE) Table II, page 5 of report LA-1339,1951. 14743 12 12 ENDBIB 10 0 14743 12 13 NOCOMMON 0 0 14743 12 14 DATA 2 1 14743 12 15 DATA DATA-ERR 14743 12 16 B B 14743 12 17 2.09 0.18 14743 12 18 ENDDATA 3 0 14743 12 19 ENDSUBENT 18 0 14743 1299999 SUBENT 14743013 20220208 149714743 13 1 BIB 5 10 14743 13 2 REACTION (26-FE-0(N,EL)26-FE-0,,SIG,,FST) 14743 13 3 DETECTOR (FISCH) 238U detector. 14743 13 4 ANALYSIS The total elastic scattering cross section obtained 14743 13 5 separately by integrating a measured angular 14743 13 6 distribution of scattered neutrons over the entire 14743 13 7 sphere. 14743 13 8 CORRECTION A correction for the loss in detection efficiency 14743 13 9 because of energy loss through elastic scattering was 14743 13 10 applied to the data for the cases of Al, Cr, and Fe. 14743 13 11 STATUS (TABLE) Table II, page 5 of report LA-1339,1951. 14743 13 12 ENDBIB 10 0 14743 13 13 NOCOMMON 0 0 14743 13 14 DATA 2 1 14743 13 15 DATA DATA-ERR 14743 13 16 B B 14743 13 17 1.97 0.25 14743 13 18 ENDDATA 3 0 14743 13 19 ENDSUBENT 18 0 14743 1399999 SUBENT 14743014 20220208 149714743 14 1 BIB 4 7 14743 14 2 REACTION (28-NI-0(N,EL)28-NI-0,,SIG,,FST) 14743 14 3 DETECTOR (FISCH) 238U detector. 14743 14 4 ANALYSIS The total elastic scattering cross section obtained 14743 14 5 separately by integrating a measured angular 14743 14 6 distribution of scattered neutrons over the entire 14743 14 7 sphere. 14743 14 8 STATUS (TABLE) Table I, page 4 of report LA-1339,1951. 14743 14 9 ENDBIB 7 0 14743 14 10 NOCOMMON 0 0 14743 14 11 DATA 2 1 14743 14 12 DATA DATA-ERR 14743 14 13 B B 14743 14 14 2.46 0.13 14743 14 15 ENDDATA 3 0 14743 14 16 ENDSUBENT 15 0 14743 1499999 SUBENT 14743015 20220208 149714743 15 1 BIB 4 7 14743 15 2 REACTION (29-CU-0(N,EL)29-CU-0,,SIG,,FST) 14743 15 3 DETECTOR (FISCH) 238U detector. 14743 15 4 ANALYSIS The total elastic scattering cross section obtained 14743 15 5 separately by integrating a measured angular 14743 15 6 distribution of scattered neutrons over the entire 14743 15 7 sphere. 14743 15 8 STATUS (TABLE) Table I, page 4 of report LA-1339,1951. 14743 15 9 ENDBIB 7 0 14743 15 10 NOCOMMON 0 0 14743 15 11 DATA 2 1 14743 15 12 DATA DATA-ERR 14743 15 13 B B 14743 15 14 2.28 0.13 14743 15 15 ENDDATA 3 0 14743 15 16 ENDSUBENT 15 0 14743 1599999 SUBENT 14743016 20220208 149714743 16 1 BIB 3 11 14743 16 2 REACTION (4-BE-9(N,INL)4-BE-9,,SIG,,FST) 14743 16 3 ANALYSIS The inelastic collision cross section is arrived at 14743 16 4 by comparing the total cross section sigmat as 14743 16 5 measuredly a transmission-type experiment with the 14743 16 6 total elastic scattering cross section obtained 14743 16 7 separately by integrating a measured angular 14743 16 8 distribution of scattered neutrons over the entire 14743 16 9 sphere. 14743 16 10 STATUS (DEP,14743002) 14743 16 11 (DEP,14743009) 14743 16 12 (TABLE) Table I, page 4 of report LA-1339,1951. 14743 16 13 ENDBIB 11 0 14743 16 14 NOCOMMON 0 0 14743 16 15 DATA 2 1 14743 16 16 DATA DATA-ERR 14743 16 17 B B 14743 16 18 0.38 0.09 14743 16 19 ENDDATA 3 0 14743 16 20 ENDSUBENT 19 0 14743 1699999 SUBENT 14743017 20220208 149714743 17 1 BIB 3 11 14743 17 2 REACTION (6-C-0(N,INL)6-C-0,,SIG,,FST) 14743 17 3 ANALYSIS The inelastic collision cross section is arrived at 14743 17 4 by comparing the total cross section sigmat as 14743 17 5 measuredly a transmission-type experiment with the 14743 17 6 total elastic scattering cross section obtained 14743 17 7 separately by integrating a measured angular 14743 17 8 distribution of scattered neutrons over the entire 14743 17 9 sphere. 14743 17 10 STATUS (DEP,14743003) 14743 17 11 (DEP,14743010) 14743 17 12 (TABLE) Table I, page 4 of report LA-1339,1951. 14743 17 13 ENDBIB 11 0 14743 17 14 NOCOMMON 0 0 14743 17 15 DATA 2 1 14743 17 16 DATA DATA-ERR 14743 17 17 B B 14743 17 18 -0.02 0.07 14743 17 19 ENDDATA 3 0 14743 17 20 ENDSUBENT 19 0 14743 1799999 SUBENT 14743018 20220208 149714743 18 1 BIB 4 14 14743 18 2 REACTION (13-AL-27(N,INL)13-AL-27,,SIG,,FST) 14743 18 3 ANALYSIS The inelastic collision cross section is arrived at 14743 18 4 by comparing the total cross section sigmat as 14743 18 5 measuredly a transmission-type experiment with the 14743 18 6 total elastic scattering cross section obtained 14743 18 7 separately by integrating a measured angular 14743 18 8 distribution of scattered neutrons over the entire 14743 18 9 sphere. 14743 18 10 CORRECTION A correction for the loss in detection efficiency 14743 18 11 because of energy loss through elastic scattering was 14743 18 12 applied to the data for the cases of Al, Cr, and Fe. 14743 18 13 STATUS (DEP,14743004) 14743 18 14 (DEP,14743011) 14743 18 15 (TABLE) Table II, page 5 of report LA-1339,1951. 14743 18 16 ENDBIB 14 0 14743 18 17 NOCOMMON 0 0 14743 18 18 DATA 2 1 14743 18 19 DATA DATA-ERR 14743 18 20 B B 14743 18 21 -0.06 0.16 14743 18 22 ENDDATA 3 0 14743 18 23 ENDSUBENT 22 0 14743 1899999 SUBENT 14743019 20220208 149714743 19 1 BIB 4 14 14743 19 2 REACTION (24-CR-0(N,INL)24-CR-0,,SIG,,FST) 14743 19 3 ANALYSIS The inelastic collision cross section is arrived at 14743 19 4 by comparing the total cross section sigmat as 14743 19 5 measuredly a transmission-type experiment with the 14743 19 6 total elastic scattering cross section obtained 14743 19 7 separately by integrating a measured angular 14743 19 8 distribution of scattered neutrons over the entire 14743 19 9 sphere. 14743 19 10 CORRECTION A correction for the loss in detection efficiency 14743 19 11 because of energy loss through elastic scattering was 14743 19 12 applied to the data for the cases of Al, Cr, and Fe. 14743 19 13 STATUS (DEP,14743005) 14743 19 14 (DEP,14743012) 14743 19 15 (TABLE) Table II, page 5 of report LA-1339,1951. 14743 19 16 ENDBIB 14 0 14743 19 17 NOCOMMON 0 0 14743 19 18 DATA 2 1 14743 19 19 DATA DATA-ERR 14743 19 20 B B 14743 19 21 0.16 0.16 14743 19 22 ENDDATA 3 0 14743 19 23 ENDSUBENT 22 0 14743 1999999 SUBENT 14743020 20220208 149714743 20 1 BIB 4 14 14743 20 2 REACTION (26-FE-0(N,INL)26-FE-0,,SIG,,FST) 14743 20 3 ANALYSIS The inelastic collision cross section is arrived at 14743 20 4 by comparing the total cross section sigmat as 14743 20 5 measuredly a transmission-type experiment with the 14743 20 6 total elastic scattering cross section obtained 14743 20 7 separately by integrating a measured angular 14743 20 8 distribution of scattered neutrons over the entire 14743 20 9 sphere. 14743 20 10 CORRECTION A correction for the loss in detection efficiency 14743 20 11 because of energy loss through elastic scattering was 14743 20 12 applied to the data for the cases of Al, Cr, and Fe. 14743 20 13 STATUS (DEP,14743006) 14743 20 14 (DEP,14743013) 14743 20 15 (TABLE) Table II, page 5 of report LA-1339,1951. 14743 20 16 ENDBIB 14 0 14743 20 17 NOCOMMON 0 0 14743 20 18 DATA 2 1 14743 20 19 DATA DATA-ERR 14743 20 20 B B 14743 20 21 0.37 0.14 14743 20 22 ENDDATA 3 0 14743 20 23 ENDSUBENT 22 0 14743 2099999 SUBENT 14743021 20220208 149714743 21 1 BIB 3 11 14743 21 2 REACTION (28-NI-0(N,INL)28-NI-0,,SIG,,FST) 14743 21 3 ANALYSIS The inelastic collision cross section is arrived at 14743 21 4 by comparing the total cross section sigmat as 14743 21 5 measuredly a transmission-type experiment with the 14743 21 6 total elastic scattering cross section obtained 14743 21 7 separately by integrating a measured angular 14743 21 8 distribution of scattered neutrons over the entire 14743 21 9 sphere. 14743 21 10 STATUS (DEP,14743007) 14743 21 11 (DEP,14743014) 14743 21 12 (TABLE) Table I, page 4 of report LA-1339,1951. 14743 21 13 ENDBIB 11 0 14743 21 14 NOCOMMON 0 0 14743 21 15 DATA 2 1 14743 21 16 DATA DATA-ERR 14743 21 17 B B 14743 21 18 1.06 0.12 14743 21 19 ENDDATA 3 0 14743 21 20 ENDSUBENT 19 0 14743 2199999 SUBENT 14743022 20220208 149714743 22 1 BIB 3 11 14743 22 2 REACTION (29-CU-0(N,INL)29-CU-0,,SIG,,FST) 14743 22 3 ANALYSIS The inelastic collision cross section is arrived at 14743 22 4 by comparing the total cross section sigmat as 14743 22 5 measuredly a transmission-type experiment with the 14743 22 6 total elastic scattering cross section obtained 14743 22 7 separately by integrating a measured angular 14743 22 8 distribution of scattered neutrons over the entire 14743 22 9 sphere. 14743 22 10 STATUS (DEP,14743008) 14743 22 11 (DEP,14743015) 14743 22 12 (TABLE) Table I, page 4 of report LA-1339,1951. 14743 22 13 ENDBIB 11 0 14743 22 14 NOCOMMON 0 0 14743 22 15 DATA 2 1 14743 22 16 DATA DATA-ERR 14743 22 17 B B 14743 22 18 0.85 0.11 14743 22 19 ENDDATA 3 0 14743 22 20 ENDSUBENT 19 0 14743 2299999 ENDENTRY 22 0 1474399999999