ENTRY 30142 20080208 31263014200000001 SUBENT 30142001 20080208 31263014200100001 BIB 14 28 3014200100002 INSTITUTE (3INDTRM) 3014200100003 REFERENCE (J,JIN,29,267,196705) Full information 3014200100004 (P,BARC-305,15,196710) Same data as JIN 29,267(1967). 3014200100005 AUTHOR (H.C.Jain,M.V.Ramaniah,C.L.Rao,Satya Prakash) 3014200100006 TITLE Fission of Ra-223 by reactor neutrons 3014200100007 FACILITY (REAC) Apsara reactor 3014200100008 INC-SPECT Pile and epicadmium neutrons. Flux density about 3014200100009 10.**12 n/cm2/sec. Irradiation time,10 hours. 3014200100010 SAMPLE 0.03 mu-gram of Ra-223 as nitrate was dried on 3014200100011 cellulose nitrate cups, wrapped in polyethylene, sealed3014200100012 in a quartz tube which was sealed in an aluminum can. 3014200100013 A blank sample was prepared under identical conditions.3014200100014 Cellulose nitrate gave no Sr-91 activation product. 3014200100015 METHOD Following irradiation and chemical isolation of Sr-91, 3014200100016 the fission cross section was estimated from Sr-91 3014200100017 activity compared with the Sr-91 activity produced in a3014200100018 known amount of simultaneously irradiated uranium.Sr-913014200100019 fission yield was assumed identical for Ra-223 and 3014200100020 uranium. 3014200100021 DETECTOR (PROPC) Gas flow proportional counter 3014200100022 MONITOR Relative to fission yield of Sr-91 from uranium3014200100023 PART-DET (FF,B-,DG) decay beta- and gammas from Sr-91 3014200100024 fission fragment yield 3014200100025 STATUS (TABLE) Datum from JIN 29(1967) p 269. 3014200100026 HISTORY (19711126C) Compiled into Exfor 3014200100027 (20080208A) BIB section updated 3014200100028 CORRECTION Background correction for unreacted Ra-223 unnecessary 3014200100029 because of successful chemical removal. 3014200100030 ENDBIB 28 0 3014200100031 COMMON 1 3 3014200100032 EN-DUMMY 3014200100033 EV 3014200100034 2.5300E-02 3014200100035 ENDCOMMON 3 0 3014200100036 ENDSUBENT 35 0 3014200199999 SUBENT 30142002 20080208 31263014200200001 BIB 2 5 3014200200002 REACTION (88-RA-223(N,F),,SIG,,SPA) 3014200200003 ERR-ANALYS (+DATA-ERR) Datum is lower limit only. If fission yield3014200200004 of Sr-91 is lower than 6%, fission cross section 3014200200005 would be higher. 3014200200006 Authors estimate by a factor of 4 or 5 at most. 3014200200007 ENDBIB 5 0 3014200200008 NOCOMMON 0 0 3014200200009 DATA 2 1 3014200200010 DATA-MIN +DATA-ERR 3014200200011 MB PER-CENT 3014200200012 7.0000E+02 5.0000E+02 3014200200013 ENDDATA 3 0 3014200200014 ENDSUBENT 13 0 3014200299999 ENDENTRY 2 0 3014299999999