ENTRY 20985 20130603 22362098500000001 SUBENT 20985001 20130603 22362098500100001 BIB 13 25 2098500100002 TITLE The thermal neutron absorption cross-section of 2098500100003 lithium-6 2098500100004 AUTHOR (M.G.Silk, B.O.Wade) 2098500100005 INSTITUTE (2UK HAR) Materials Physics Division 2098500100006 REFERENCE (R,AERE-M-2366,1970) 2098500100007 FACILITY No information 2098500100008 INC-SOURCE (D-T) 14 MeV neutron source 2098500100009 REL-REF (I,20460001,M.G.Silk+,J,JNE,23,1,1969) 2098500100010 Description of detector and multiscaler system 2098500100011 (I,,M.W.Rampling,R,AERE-M-1498,1965) 2098500100012 Description of pulsed-neutron source 'Elliot K-tube' 2098500100013 SAMPLE (3-LI-6,ENR=0.9576) Reactor grade D2O poisoned with 2098500100014 304.0 +/- 0.5 g of enriched (95.76+/-0.04%) 6Li 2098500100015 carbonate contained in a large cylindrical steel tank 2098500100016 DETECTOR (SCIN) Two liquid NE311 scintillation counters 2098500100017 (2 inch diam. x 1 1/2 inch thick.) 2098500100018 METHOD (SLODT) Decay constant of fast pulse neutrons injected 2098500100019 to the system reaching to equilibrium with the 2098500100020 temperature of the moderator was determined, and then 2098500100021 the absorption cross section was derived from the 2098500100022 interpolation of the decay constant to an infinite 2098500100023 system. 2098500100024 ADD-RES Diffusion constant of pure D2O (2.014+/-0.010)E+5 cm2/s2098500100025 ERR-ANALYS (DATA-ERR) No information on source of uncertainties 2098500100026 HISTORY (20130603C) On 2098500100027 ENDBIB 25 0 2098500100028 NOCOMMON 0 0 2098500100029 ENDSUBENT 28 0 2098500199999 SUBENT 20985002 20130603 22362098500200001 BIB 2 2 2098500200002 REACTION (3-LI-6(N,ABS),,SIG) 2098500200003 STATUS (TABLE) Text (p.2) of AERE-M-2366 2098500200004 ENDBIB 2 0 2098500200005 NOCOMMON 0 0 2098500200006 DATA 3 1 2098500200007 EN DATA DATA-ERR 2098500200008 EV B B 2098500200009 0.0253 943.8 2.8 2098500200010 ENDDATA 3 0 2098500200011 ENDSUBENT 10 0 2098500299999 ENDENTRY 2 0 2098599999999