ENTRY 21917 20070512 21852191700000001 SUBENT 21917001 20070512 21852191700100001 BIB 16 54 2191700100002 INSTITUTE (2GERMUN) Instutute fuer Radiochemie, Technische 2191700100003 Universitaet, Muenchen 2191700100004 REFERENCE (J,RCA,30,(1),19,1982) 2191700100005 AUTHOR (D.C.Aumann,L.Friedmann) 2191700100006 TITLE -Cumulative yield of 1.6E+07 I-129 from thermal- 2191700100007 neutron induced fission of U-235- 2191700100008 FACILITY (REAC ,2GERMUN) The Munich research reactor 2191700100009 INC-SOURCE (REAC ) The samples were irradiated in the 2191700100010 graphite replector of the Munich research reactor 2191700100011 INC-SPECT .The thermal neutron flux in the irradiation position 2191700100012 was 1.2E+13 neutrons/cm-sq*sec 2191700100013 SAMPLE .A chip of 118.5 mg uranium metal enriched to 90 2191700100014 per cent in U-235 was enclosed in a small ampoule 2191700100015 of high purity quartz which itself was sealed in 2191700100016 an aluminum can. The space between the ampoule and 2191700100017 the aluminum can was filled with coarse-grained 2191700100018 aluminum powder 2191700100019 METHOD (INTB ) Irradiation time 80 min 2191700100020 (CHSEP) Chemical separation of produced I-129 after a 2191700100021 decay time of about 5 months 2191700100022 (ACTIV) Activation of separated iodine for 2 hr. 2191700100023 DETECTOR (GELI ) Coaxial Ge(Li) with a resolution of 2.1 MeV 2191700100024 for the 1.33 MeV gamma ray of Co-60 used for 2191700100025 detection of gamma rays from the decay of I-130 and 2191700100026 of gamma rays from the decay of the fission product 2191700100027 Ce-144 used for determination of the number of 2191700100028 fissions 2191700100029 ANALYSIS .The number of produced I-129 atoms was estimated from 2191700100030 the number of I-130 atoms produced in an irradiation 2191700100031 of the chemically separated Pb-I2. The cross section 2191700100032 used for the reaction 53-I-129(N,g)53-I-130 was 2191700100033 30.4+-1.7 barns. 2191700100034 .The number of fissions induced in the irradiated 2191700100035 U-235 sample was determined by an absolute 2191700100036 measurement of the Ce-144 content. An absolute yield 2191700100037 of 5.37 per cent for Ce-144 in thermal-neutron 2191700100038 induced fission was used. 2191700100039 ASSUMED (ASSUM,53-I-129(N,G)53-I-130,,SIG) Used in ANALYSIS 2191700100040 STATUS .Data were taken from main reference 2191700100041 CORRECTION .For 2191700100042 - detector efficiency 2191700100043 - chemical yield of fission products 2191700100044 ERR-ANALYS (DATA-ERR) The overall uncertainty of the yield value 2191700100045 was estimated from errors in the 2191700100046 - activity measurements 2191700100047 - detector efficiency calibration 2191700100048 - chemical yield determination 2191700100049 - neutron flux measurements 2191700100050 - cross section of the reaction 53-I-129(N,g)53-I-130 2191700100051 - measurement of the fission rate 2191700100052 HISTORY (19840425C) A.L. 2191700100053 (19840710E) 2191700100054 (20070512A) Date is corrected 2191700100055 (20070712U) Last corrections have been done - SM 2191700100056 ENDBIB 54 0 2191700100057 COMMON 3 3 2191700100058 EN-DUMMY ASSUM ASSUM-ERR 2191700100059 EV B B 2191700100060 2.53E-02 30.4 1.7 2191700100061 ENDCOMMON 3 0 2191700100062 ENDSUBENT 61 0 2191700199999 SUBENT 21917002 20070512 21852191700200001 BIB 6 8 2191700200002 REACTION (92-U-235(N,F)53-I-129,CUM,FY,,MXW) 2191700200003 DECAY-DATA (53-I-130,12.3HR,DG,536.,.997,DG,668.,.969, 2191700200004 DG,739.,.829) I-130 produced after 2191700200005 an irradiation of chemically separated I-129 2191700200006 MONITOR (92-U-235(N,F)58-CE-144,IND,FY,,MXW) 2191700200007 DECAY-MON (59-PR-144,17.30MIN,DG,696.5,.01342) 2191700200008 STATUS .Data were taken from main reference 2191700200009 HISTORY (20070512A) Units corrected to PC/FIS 2191700200010 ENDBIB 8 0 2191700200011 NOCOMMON 0 0 2191700200012 DATA 2 1 2191700200013 DATA DATA-ERR 2191700200014 PC/FIS PC/FIS 2191700200015 6.9E-01 5.E-02 2191700200016 ENDDATA 3 0 2191700200017 ENDSUBENT 16 0 2191700299999 ENDENTRY 2 0 2191799999999