ENTRY 21721 20101118 22252172100000001 SUBENT 21721001 20101118 22252172100100001 BIB 15 52 2172100100002 INSTITUTE (2BLGGHT) Institute for Nuclear Sciences. 2172100100003 (2BLGMOL) Reactor site. 2172100100004 REFERENCE (J,RCA,7,198,1967) full report. 2172100100005 AUTHOR (M.Deschuyter,J.Hoste) 2172100100006 TITLE -Mean reactor cross sections for (n,p) reactions 2172100100007 on titanium -. 2172100100008 FACILITY (REAC,2BLGMOL) BR-1 reactor, MOL. 2172100100009 INC-SOURCE (REAC ) irradiations with and without cadmium cover 2172100100010 in BR-1 reactor for 2 hours. Thermal and epithermal 2172100100011 reactor neutrons. 2172100100012 INC-SPECT .From irradiations with Co and Au monitors 2172100100013 fast neutron component of the graphite reactor, BR-1 2172100100014 gives an equivalent fission flux identical to a pure 2172100100015 fission flux. 2172100100016 SAMPLE .Known amounts of about 100 mg of titanium oxide, 2172100100017 packed in quartz vials. 2172100100018 .Analytical grade ammonium sulphate was used as the 2172100100019 monitor sample. 2172100100020 .Scandium standards with and without cadmium cover 2172100100021 were used to correct for Sc-45 produced by the neutron2172100100022 capture reaction. 2172100100023 METHOD (ACTIV,CHSEP) activation, following radiochemical 2172100100024 separation of titanium. The TiO2 matrix was dissolved2172100100025 in sulfuric acid and ammonium sulphate, titanium 2172100100026 precipitated with excess ammonia, and impurities 2172100100027 removed by cation exchange column. Titanium reaction 2172100100028 activities measured by decay gammas. 2172100100029 DETECTOR (NAICR) calibrated 3 by 3 inch NaI(Tl) scintillator 2172100100030 crystal. 2172100100031 MONITOR (16-S-32(N,P)15-P-32,,SIG,,FIS) fast neutron flux 2172100100032 monitored by the disintegration rate of P-32, formed 2172100100033 by the (n,p) reaction on S-32 in ammonium sulphate, 2172100100034 by liquid scintillator in the presence of the 2172100100035 unseparated sulphur matrix. No value for this monitor 2172100100036 cross section is given. 2172100100037 CORRECTION .Corrected for Sc-45 from neutron capture. Several 2172100100038 corrections were also made because the 1.33 MeV peak 2172100100039 of Sc-48 is perturbed by the Compton contribution of 2172100100040 its own sumpeak and of those of Sc-46 as well as the 2172100100041 contribution of the 2.32 MeV sumpeak resulting from 2172100100042 summing the 1.33 and 0.99 MeV gammas. The net 2172100100043 correction was 10%. 2172100100044 ERR-ANALYS (DATA-ERR) the estimated total error is 15%, 2172100100045 mainly due to the uncertainty associated with the 2172100100046 cross section value of the fast flux monitor. 2172100100047 STATUS (TABLE).Final values in Tbl.3, page 201, 2172100100048 RadioCh.Acta,7,198,1967. 2172100100049 HISTORY (19810111C) 2172100100050 (19810120E) 2172100100051 (20101114A) SD:Updated to new date formats,lower case. 2172100100052 corrected according to last EXFOR rules and Dict. 2172100100053 Code SUM deleted from REACTION (Subent 002) 2172100100054 ENDBIB 52 0 2172100100055 COMMON 1 3 2172100100056 EN-DUMMY 2172100100057 MEV 2172100100058 1.5000E+00 2172100100059 ENDCOMMON 3 0 2172100100060 ENDSUBENT 59 0 2172100199999 SUBENT 21721002 20101118 22252172100200001 BIB 2 6 2172100200002 REACTION (22-TI-46(N,P)21-SC-46,,SIG,,FIS) fission average 2172100200003 DECAY-DATA (21-SC-46-G,84.D,DG,1120.,,DG,890.) counted after 2172100200004 a cooling period of several months to ensure complete 2172100200005 decay of Sc-47 and Sc-48. 2172100200006 the metastable state decays almost 100% by 2172100200007 internal transitions with a half-life of 20 secs. 2172100200008 ENDBIB 6 0 2172100200009 NOCOMMON 0 0 2172100200010 DATA 2 1 2172100200011 DATA DATA-ERR 2172100200012 MB MB 2172100200013 8.6000E+00 1.4000E+00 2172100200014 ENDDATA 3 0 2172100200015 ENDSUBENT 14 0 2172100299999 SUBENT 21721003 20101118 22252172100300001 BIB 2 3 2172100300002 REACTION (22-TI-47(N,P)21-SC-47,,SIG,,FIS) fission average 2172100300003 DECAY-DATA (21-SC-47,3.4D,DG,159.) activity corrected for 2172100300004 Sc-46 and Sc-48. 2172100300005 ENDBIB 3 0 2172100300006 NOCOMMON 0 0 2172100300007 DATA 2 1 2172100300008 DATA DATA-ERR 2172100300009 MB MB 2172100300010 1.8200E+01 2.6000E+00 2172100300011 ENDDATA 3 0 2172100300012 ENDSUBENT 11 0 2172100399999 SUBENT 21721004 20101118 22252172100400001 BIB 2 3 2172100400002 REACTION (22-TI-48(N,P)21-SC-48,,SIG,,FIS) fission average 2172100400003 DECAY-DATA (21-SC-48,44.HR,DG,990.,1.0,DG,1040.,1.0,DG,1310.,1.0) 2172100400004 1.33 MeV photopeak counted. 2172100400005 ENDBIB 3 0 2172100400006 NOCOMMON 0 0 2172100400007 DATA 2 1 2172100400008 DATA DATA-ERR 2172100400009 MB MB 2172100400010 1.1000E-01 1.0000E-02 2172100400011 ENDDATA 3 0 2172100400012 ENDSUBENT 11 0 2172100499999 ENDENTRY 4 0 2172199999999