ENTRY T0158 20010622 0000T015800000001 SUBENT T0158001 20010622 0000T015800100001 BIB 13 31 T015800100002 INSTITUTE (1CANCRC,1CANMCG) T015800100003 REFERENCE (J,NIM,214,333,1983) T015800100004 AUTHOR (M.A.Lone,R.T.Jones,A.Okazaki,B.M.Townes,D.C.Santry, T015800100005 E.D.Earle,J.K.P.Lee,J.M.Robson,R.B.Moore,L.Nikkinen, T015800100006 V.Raut) T015800100007 TITLE Total Neutron Yields from 100 MeV Protons on Pb and T015800100008 7Li Targets. T015800100009 FACILITY (SYNCY,1CANMCG) T015800100010 METHOD (BCINT) Typical average beam currents during an T015800100011 irradiation were 50 nA with an estimated overall T015800100012 uncertainty of <1.5%. T015800100013 DETECTOR (MTANK) Large tank in the form of a vertical T015800100014 cyclinder (1.7-m high by 1.5-m diameter). T015800100015 Gamma activity of the Au foils was counted on an T015800100016 automatic system with two NaI(Tl) detectors. T015800100017 MONITOR (79-AU-197(N,G)79-AU-198,,INT) T015800100018 Thermal neutron flux distribution inside the water T015800100019 tank was measured by activating gold foils. T015800100020 Macroscopic (n,gamma) cross section of 197Au for 2200 T015800100021 m/sec velocity neutrons was assumed as 5.835 1/cm. T015800100022 CORRECTION Flux in tank corrected for measure dazimuthal T015800100023 variations. T015800100024 ERR-ANALYS (DATA-ERR) Separate error analysis in which statisticalT015800100025 and systematic errors were assigned to each of the T015800100026 separate factors needed to derive the measured yield T015800100027 indicated a an overall uncertainty of +-6%. T015800100028 ADD-RES (COMP) Data are compared with theoretical results T015800100029 from the computer codes NMTC and MORSE. T015800100030 STATUS Data taken from Table 2 in reference. T015800100031 (APRVD) Approved by A. Lone, 20 June 2001. T015800100032 HISTORY (20010613C) SB+VM T015800100033 ENDBIB 31 0 T015800100034 NOCOMMON 0 0 T015800100035 ENDSUBENT 34 0 T015800199999 SUBENT T0158002 20010613 0000T015800200001 BIB 3 8 T015800200002 REACTION (3-LI-7(P,X)0-NN-1,,PY) T015800200003 SAMPLE Thick targets of Li, enriched to 99.995% 7Li, 17.4-cm T015800200004 long by 5.7-cm diameter. T015800200005 CORRECTION Yields corrected for T015800200006 . thermal neutron absortion in target and target tube T015800200007 (<1%), T015800200008 . absorption of non-thermal neutrons (about 1.9%), T015800200009 . leakage of neutrons of all energies (0.5%). T015800200010 ENDBIB 8 0 T015800200011 NOCOMMON 0 0 T015800200012 DATA 3 1 T015800200013 EN DATA DATA-ERR T015800200014 MEV PRD/INC PRD/INC T015800200015 100. 0.123 0.007 T015800200016 ENDDATA 3 0 T015800200017 ENDSUBENT 16 0 T015800299999 SUBENT T0158003 20020124 0000T015800300001 BIB 5 9 T015800300002 REACTION (82-PB-0(P,X)0-NN-1,,PY) T015800300003 SAMPLE Thick targets of Pb, 1.6-cm long by 6.2-cm diameter. T015800300004 ANALYSIS Average of values from three measurements. T015800300005 CORRECTION Yields corrected for T015800300006 . thermal neutron absortion in target and target tube T015800300007 (<1%), T015800300008 . absorption of non-thermal neutrons (about 1.4%), T015800300009 . leakage of neutrons of all energies (0.3%). T015800300010 HISTORY (20020124A) Data error heading corrected. T015800300011 ENDBIB 9 0 T015800300012 NOCOMMON 0 0 T015800300013 DATA 3 1 T015800300014 EN DATA DATA-ERR T015800300015 MEV PRD/INC PRD/INC T015800300016 100. 0.343 0.021 T015800300017 ENDDATA 3 0 T015800300018 ENDSUBENT 17 0 T015800399999 ENDENTRY 3 0 T015899999999