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