ENTRY 22515 20200920 22912251500000001 SUBENT 22515001 20200920 22912251500100001 BIB 14 36 2251500100002 TITLE The cross section of the reaction 6Li(n,p)6He 2251500100003 in the neutron energy range 3.5 to 14.8 MeV 2251500100004 AUTHOR (J.F.Barry) 2251500100005 REFERENCE (J,JNE/AB,17,273,1963) 2251500100006 INSTITUTE (2UK ALD) 2251500100007 FACILITY (VDG,2UK ALD) 2251500100008 INC-SOURCE (D-D) For the neutron energy range 3.5 to 8.6 MeV a gas2251500100009 target was employed which was 2.5 cm long and was 2251500100010 filled with deuterium at approximately 1 atm pressure. 2251500100011 (D-T) Neutrons of energy 14.8 MeV were obtained by 2251500100012 bombarding a thick titanium tritide target with 2251500100013 300 keV deuterons. 2251500100014 INC-SPECT (EN-RSL-HW) The spread in neutron energy was calculated2251500100015 from the target thickness and the angle subtended by 2251500100016 the sample at the target using the reaction data of 2251500100017 Fowler and Brolley (see REL-REF). 2251500100018 METHOD (ACTIV) 2251500100019 MONITOR (92-U-235(N,F),,SIG) for neutron flux 2251500100020 SAMPLE (3-LI-6,ENR=0.93) The lithium sample, enriched to 93% 2251500100021 6Li and of 99.8% chemical purity, was in the form of 2251500100022 a disk 1.6 cm dia. by 0.125 cm thick in an aluminium 2251500100023 can with a wall thickness of O.025 cm. 2251500100024 DETECTOR (PROPC) Beta particles from the decay of 6He were 2251500100025 counted in an end-window, gas-flow, proportional 2251500100026 counter. 2251500100027 REL-REF (R,,J.L.Fowler+,J,RMP,28,103,1956) 2251500100028 ERR-ANALYS (DATA-ERR) The errors include: 2251500100029 * the counting statistics error and 2251500100030 * the estimated error in the neutron flux 2251500100031 determinations and Beta-particle counter 2251500100032 calibration. 2251500100033 HISTORY (19820331C) ! ! Compiled by NNDC 2251500100034 (19991210C) + + Converted by S.M. + + 2251500100035 (20060806U) Reference code corrected 2251500100036 (20200920A) SD: BIB updated. Corrections in all Subents2251500100037 The accuracy of data presentation has been revised. 2251500100038 ENDBIB 36 0 2251500100039 NOCOMMON 0 0 2251500100040 ENDSUBENT 39 0 2251500199999 SUBENT 22515002 20200920 22912251500200001 BIB 3 5 2251500200002 REACTION (3-LI-7(N,X)2-HE-6,,SIG) 2251500200003 STATUS (TABLE) text from p.275 of J.Nucl.En.,A/B17(1963)273 2251500200004 HISTORY (19991210T) Converted from Subent 60434003 2251500200005 (20200920A) SD: SF3=D -> X in REACTION code. STATUS 2251500200006 added. EN-RSL added. 2251500200007 ENDBIB 5 0 2251500200008 NOCOMMON 0 0 2251500200009 DATA 5 1 2251500200010 EN -EN-RSL +EN-RSL DATA DATA-ERR 2251500200011 MEV MEV MEV MB MB 2251500200012 14.8 0.2 0.5 14. 1.5 2251500200013 ENDDATA 3 0 2251500200014 ENDSUBENT 13 0 2251500299999 SUBENT 22515003 20200920 22912251500300001 BIB 3 4 2251500300002 REACTION (3-LI-6(N,P)2-HE-6,,SIG) 2251500300003 STATUS (TABLE) Tbl.1 from J.Nucl.En.,A/B17(1963)273 2251500300004 HISTORY (19991210T) Converted from Subent 60434003 2251500300005 (20200920A) SD: STATUS added. EN-RSL added. 2251500300006 ENDBIB 4 0 2251500300007 NOCOMMON 0 0 2251500300008 DATA 5 7 2251500300009 EN -EN-RSL +EN-RSL DATA DATA-ERR 2251500300010 MEV MEV MEV MB MB 2251500300011 3.5 0.3 0.19 4.5 0.5 2251500300012 3.87 0.3 0.13 13.8 1.4 2251500300013 5.9 0.27 0.11 18.2 1.8 2251500300014 6.7 0.27 0.16 16.6 1.7 2251500300015 7.75 0.35 0.17 15. 1.5 2251500300016 8.59 0.38 0.2 14.8 1.8 2251500300017 14.8 0.2 0.5 7.1 0.7 2251500300018 ENDDATA 9 0 2251500300019 ENDSUBENT 18 0 2251500399999 ENDENTRY 3 0 2251599999999