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