ENTRY 21508 20101114 22252150800000001 SUBENT 21508001 20101114 22252150800100001 BIB 15 35 2150800100002 INSTITUTE (2GERMUN) 2150800100003 REFERENCE (J,NUK,8,(1),9,1965) 2150800100004 AUTHOR (W.Koehler) 2150800100005 TITLE -Determination of the effective cross section of 2150800100006 the Ti-46(n,p)Sc-46 reaction for a light water 2150800100007 moderated reactor.- (In German).- 2150800100008 FACILITY (REAC,2GERMUN) Reactor station Garching. 2150800100009 INC-SOURCE (REAC ) Reactor neutrons. 2150800100010 INC-SPECT Fission neutrons. 2150800100011 SAMPLE .Metallic natural Ti strips (3 mm *20 mm *0.075 mm) 2150800100012 (NH4)2SO4 used as monitor sample, 120 mg 2150800100013 melted into small glassampoules (6 cm long, 0.5 cm 2150800100014 diam). 90 samples were used. About 45 of them were 2150800100015 covered with Cd, 0.5 mm thick to estimate the 2150800100016 contributions from Sc and P impurities in sample 2150800100017 and monitor. 2150800100018 METHOD (ACTIV,COINC) Activation measurements with and without 2150800100019 Cd cover for the sample. The yields of the reaction 2150800100020 are isolated by the determination of the beta 2150800100021 absorption curves. 2150800100022 DETECTOR .Beta-gamma and 4*Pi beta-gamma coincidence apparatus. 2150800100023 MONITOR (16-S-32(N,P)15-P-32,,SIG,,FIS) 2150800100024 CORRECTION .Impurities. 2150800100025 ERR-ANALYS (DATA-ERR) .Error compounded from statistical error, 2150800100026 error on sample weight, error on half life, error on 2150800100027 post irradiation cooling time. 2150800100028 STATUS (NDD ) Data taken from NEUDADA. 2150800100029 (TABLE) Tbl. 1 of J,NUK,8,9,1965 2150800100030 HISTORY (19800416T) G.C. 2150800100031 (19800429E) 2150800100032 (20101114A) SD:Updated to new date formats,lower case. 2150800100033 corrected according to last EXFOR rules and Dict. 2150800100034 Code SUM deleted from REACTION (Subent 002) 2150800100035 STATUS and HISTORY deleted from Subents 002-004 2150800100036 Ref.corrected: NUK,8,1,9,1965 => NUK,8,(1),9,1965 2150800100037 ENDBIB 35 0 2150800100038 COMMON 2 3 2150800100039 EN-DUMMY MONIT 2150800100040 MEV MB 2150800100041 1.5000E+00 6.6000E+01 2150800100042 ENDCOMMON 3 0 2150800100043 ENDSUBENT 42 0 2150800199999 SUBENT 21508002 20101114 22252150800200001 BIB 2 2 2150800200002 REACTION (22-TI-46(N,P)21-SC-46,,SIG,,FIS) 2150800200003 DECAY-DATA (21-SC-46-G,86.D,B) 2150800200004 ENDBIB 2 0 2150800200005 NOCOMMON 0 0 2150800200006 DATA 2 1 2150800200007 DATA DATA-ERR 2150800200008 MB MB 2150800200009 1.2600E+01 4.0000E-01 2150800200010 ENDDATA 3 0 2150800200011 ENDSUBENT 10 0 2150800299999 SUBENT 21508003 20101114 22252150800300001 BIB 2 2 2150800300002 REACTION (22-TI-47(N,P)21-SC-47,,SIG,,FIS) 2150800300003 DECAY-DATA (21-SC-47,3.4D,B) 2150800300004 ENDBIB 2 0 2150800300005 NOCOMMON 0 0 2150800300006 DATA 2 1 2150800300007 DATA DATA-ERR 2150800300008 MB MB 2150800300009 1.3200E+01 1.0000E+00 2150800300010 ENDDATA 3 0 2150800300011 ENDSUBENT 10 0 2150800399999 SUBENT 21508004 20101114 22252150800400001 BIB 2 2 2150800400002 REACTION (22-TI-48(N,P)21-SC-48,,SIG,,FIS) 2150800400003 DECAY-DATA (21-SC-48,1.8D,B) 2150800400004 ENDBIB 2 0 2150800400005 NOCOMMON 0 0 2150800400006 DATA 2 1 2150800400007 DATA DATA-ERR 2150800400008 MB MB 2150800400009 3.3000E+00 2.0000E-01 2150800400010 ENDDATA 3 0 2150800400011 ENDSUBENT 10 0 2150800499999 ENDENTRY 4 0 2150899999999