ENTRY 21393 20120917 22342139300000001 SUBENT 21393001 20120917 22342139300100001 BIB 10 21 2139300100002 REFERENCE (J,CJC,34,293,1956) 2139300100003 TITLE The yields of I-129 in natural and in neutron 2139300100004 induced fission of uranium 2139300100005 AUTHOR (B.C.Purkayastha,G.R.Martin) 2139300100006 INSTITUTE (2UK DUR) 2139300100007 METHOD (ACTIV,RCHEM) Radioactivation technique 2139300100008 DETECTOR (GEMUC) Geiger-Muller tube. 2139300100009 SAMPLE .Iodine extracted from pitchblende and from pile 2139300100010 irradiated uranium metal. 2139300100011 CORRECTION .Corrected for contaminations with similar half 2139300100012 lives such as Na-24, K-42 etc. Also corrected for 2139300100013 losses due to finite resolving power of counter, 2139300100014 self absorption in sample, radioactive decay, and 2139300100015 chemical yield in separation procedures. 2139300100016 ERR-ANALYS .No errors given. 2139300100017 HISTORY (19800229C) 2139300100018 (19800303E) 2139300100019 (19890907A) CUM not IND yields in subents 3 and 4 2139300100020 (19890919E) 2139300100021 (20120917A) SD: Updated to new date formats,lower case.2139300100022 Corrected according last EXFOR rules and Dict. 2139300100023 ENDBIB 21 0 2139300100024 NOCOMMON 0 0 2139300100025 ENDSUBENT 24 0 2139300199999 SUBENT 21393002 20120917 22342139300200001 BIB 7 17 2139300200002 REACTION (53-I-129(N,G)53-I-130-G,,SIG,,MXW) Capture cross 2139300200003 section for pile neutrons. 2139300200004 FACILITY (REAC,2UK HAR) BEPO reactor at A.E.R.E. Harwell. 2139300200005 INC-SPECT Maxwellian pile spectrum. 2139300200006 Neutron flux of ~ 1.5 x 10**12 n/cm2/sec 2139300200007 SAMPLE The elementary iodine contained in the small silica 2139300200008 ampoule prepared by radioactivation analysis was sent 2139300200009 for irradiation together with 2139300200010 (a) a weighed sample of isotopically normal lead 2139300200011 iodide, and 2139300200012 (b) a weighed piece of thin copper wire, each being 2139300200013 contained in similar silica ampoules, all of which2139300200014 were placed within the same aluminum capsule for 2139300200015 irradiation. 2139300200016 DECAY-DATA (53-I-130-G,12.6HR,B-) 2139300200017 MONITOR (29-CU-63(N,G)29-CU-64,,SIG,,MXW) For flux monitor. 2139300200018 STATUS (TABLE) Data from the text of Can.J.Chem.,34,293,1956 2139300200019 ENDBIB 17 0 2139300200020 NOCOMMON 0 0 2139300200021 DATA 3 1 2139300200022 EN-DUMMY MONIT DATA 2139300200023 EV B B 2139300200024 2.5300E-02 4.2400E+00 3.5000E+01 2139300200025 ENDDATA 3 0 2139300200026 ENDSUBENT 25 0 2139300299999 SUBENT 21393003 20120917 22342139300300001 BIB 7 13 2139300300002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) Maxwellian 2139300300003 average cumulative fission product yield. 2139300300004 FACILITY (REAC,2UK HAR) BEPO reactor at A.E.R.E. Harwell. 2139300300005 INC-SPECT Maxwellian pile spectrum. 2139300300006 Neutron flux of ~ 1.5 x 10**12 n/cm2/sec 2139300300007 SAMPLE Three 5 mg. pieces of uranium metal 2139300300008 COMMENT .Derived from the ratio of I-130 activity induced 2139300300009 by neutron capture in a known mass of I-129 to that 2139300300010 induced in samples of iodine extracted from neutron 2139300300011 irradiated uranium. 2139300300012 STATUS (TABLE) Data from the text of Can.J.Chem.,34,293,1956 2139300300013 HISTORY (19890907A) CUM not IND yields 2139300300014 (19890919E) 2139300300015 ENDBIB 13 0 2139300300016 NOCOMMON 0 0 2139300300017 DATA 4 1 2139300300018 EN-DUMMY ELEMENT MASS DATA 2139300300019 EV NO-DIM NO-DIM PC/FIS 2139300300020 2.5300E-02 5.3000E+01 1.2900E+02 9.0000E-01 2139300300021 ENDDATA 3 0 2139300300022 ENDSUBENT 21 0 2139300399999 SUBENT 21393004 20120917 22342139300400001 BIB 7 13 2139300400002 REACTION (92-U-235(0,F)ELEM/MASS,CUM,FY) Spontaneous 2139300400003 cumulative fission yields. 2139300400004 SAMPLE Sample 1. U3O8 in mineral (82%) 2139300400005 Sample 2. U3O8 in mineral (64%) 2139300400006 MONITOR (92-U-235(0,F)54-XE-136,CUM,FY) Yield of Xe-136. 2139300400007 ANALYSIS .Derived from ratio of I-129 and Xe-136 yields from 2139300400008 samples of pitchblende. 2139300400009 FLAG (1.) Sample 1 2139300400010 (2.) Sample 2 2139300400011 STATUS (TABLE) Data from Tbl. II of Can.J.Chem.,34,293,1956 2139300400012 HISTORY (19890907A) CUM not IND yields 2139300400013 (19890919E) 2139300400014 (20120917A) SD: Data from Tbl.2 was added with FLAG. 2139300400015 ENDBIB 13 0 2139300400016 NOCOMMON 0 0 2139300400017 DATA 5 2 2139300400018 ELEMENT MASS MONIT DATA FLAG 2139300400019 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 2139300400020 5.3000E+01 1.2900E+02 6.5000E+00 4.8000E-01 1. 2139300400021 5.3000E+01 1.2900E+02 6.5000E+00 5.4000E-01 2. 2139300400022 ENDDATA 4 0 2139300400023 ENDSUBENT 22 0 2139300499999 ENDENTRY 4 0 2139399999999