ENTRY            13481   19920508                             00001348100000001 
SUBENT        13481001   19920508                             00001348100100001 
BIB                 10         17                                 1348100100002 
INSTITUTE  (1CANMCM)                                              1348100100003 
REFERENCE  (J,CJP,47,1409,6907)                                   1348100100004 
AUTHOR     (J.R.DE LAETER,H.G.THODE)                              1348100100005 
TITLE      RELATIVE YIELDS OF STABLE TIN ISOTOPES IN NEUTRON-     1348100100006 
            INDUCED FISSION                                       1348100100007 
METHOD     (CHSEP,ASEP)                                           1348100100008 
CORRECTION CORRECTED FOR:                                         1348100100009 
           - TERRESTRIAL TIN CONTAMINATION                        1348100100010 
           - SPECTROMETER-INDUCED MASS DISCRIMINATION EFFECTS     1348100100011 
ERR-ANALYS (DATA-ERR) MAINLY DUE TO CORRECTIONS AND SMALL AMOUNT  1348100100012 
            OF SIN AVAIBLE FOR ANALYSIS                           1348100100013 
CRITIQUE   DOES NOT AGREE WITH LATER MEASUREMENT OF ROSMAN,       1348100100014 
            DE LAETER, ET AL., CAN.J.PHYS. 61, 1490 (1983).       1348100100015 
            AUTHORS RECOMMEND USE OF LATTER SINCE BETTER          1348100100016 
            MASS SPECTROMETRIC TECHNIQUES WERE USED.              1348100100017 
STATUS     DATA TAKEN FROM ARTICLE                                1348100100018 
HISTORY    (920508C)                                              1348100100019 
ENDBIB              17          0                                 1348100100020 
NOCOMMON             0          0                                 1348100100021 
ENDSUBENT           20          0                                 1348100199999 
SUBENT        13481002   19920508                             00001348100200001 
BIB                  4          5                                 1348100200002 
REACTION   ((92-U-233(N,F)ELEM/MASS,CUM,FY,,SPA)/                 1348100200003 
           (92-U-233(N,F)50-SN-126,CUM,FY,,SPA))                  1348100200004 
FACILITY   (REAC,1CANMCM) MC MASTER UNIVERSITY REACTOR            1348100200005 
SAMPLE     3 U(3)O(8) SAMPLES                                     1348100200006 
METHOD     SAMPLES IRRADIATED FOR 30 DAYS.  COOLING TIME 45 DAYS. 1348100200007 
ENDBIB               5          0                                 1348100200008 
COMMON               2          3                                 1348100200009 
EN-DUMMY   ELEMENT                                                1348100200010 
EV         NO-DIM                                                 1348100200011 
 0.0253     50.                                                   1348100200012 
ENDCOMMON            3          0                                 1348100200013 
DATA                 3          6                                 1348100200014 
MASS       DATA       DATA-ERR                                    1348100200015 
NO-DIM     NO-DIM     NO-DIM                                      1348100200016 
117.        0.180      0.013                                      1348100200017 
118.        0.186      0.013                                      1348100200018 
119.        0.189      0.014                                      1348100200019 
120.        0.210      0.014                                      1348100200020 
122.        0.234      0.013                                      1348100200021 
124.        0.386      0.020                                      1348100200022 
ENDDATA              8          0                                 1348100200023 
ENDSUBENT           22          0                                 1348100299999 
SUBENT        13481003   19920508                             00001348100300001 
BIB                  4          5                                 1348100300002 
REACTION   ((92-U-233(N,F)ELEM/MASS,CUM,FY,,FST)/                 1348100300003 
           (92-U-233(N,F)50-SN-126,CUM,FY,,FST))                  1348100300004 
FACILITY   (REAC,1CANMCM) MC MASTER UNIVERSITY REACTOR            1348100300005 
SAMPLE     3 CD-WRAPPED U(3)O(8) SAMPLES                          1348100300006 
METHOD     SAMPLES IRRADIATED FOR 90 DAYS.  COOLING TIME 45 DAYS. 1348100300007 
ENDBIB               5          0                                 1348100300008 
COMMON               2          3                                 1348100300009 
EN-DUMMY   ELEMENT                                                1348100300010 
EV         NO-DIM                                                 1348100300011 
 1.0        50.                                                   1348100300012 
ENDCOMMON            3          0                                 1348100300013 
DATA                 3          6                                 1348100300014 
MASS       DATA       DATA-ERR                                    1348100300015 
NO-DIM     NO-DIM     NO-DIM                                      1348100300016 
117.        0.21       0.02                                       1348100300017 
118.        0.21       0.02                                       1348100300018 
119.        0.26       0.03                                       1348100300019 
120.        0.29       0.03                                       1348100300020 
122.        0.29       0.03                                       1348100300021 
124.        0.42       0.04                                       1348100300022 
ENDDATA              8          0                                 1348100300023 
ENDSUBENT           22          0                                 1348100399999 
SUBENT        13481004   19920508                             00001348100400001 
BIB                  4          5                                 1348100400002 
REACTION   ((92-U-0(N,F)ELEM/MASS,CUM,FY,,SPA)/                   1348100400003 
           (92-U-0(N,F)50-SN-126,CUM,FY,,SPA))                    1348100400004 
FACILITY   (REAC,1CANCRC) NRX REACTOR.                            1348100400005 
SAMPLE     NATURAL URANIUM FUEL ROD                               1348100400006 
METHOD     IRRADIATED FOR ABOUT 5 YEARS.                          1348100400007 
ENDBIB               5          0                                 1348100400008 
COMMON               2          3                                 1348100400009 
EN-DUMMY   ELEMENT                                                1348100400010 
EV         NO-DIM                                                 1348100400011 
 0.0253     50.                                                   1348100400012 
ENDCOMMON            3          0                                 1348100400013 
DATA                 3          6                                 1348100400014 
MASS       DATA       DATA-ERR                                    1348100400015 
NO-DIM     NO-DIM     NO-DIM                                      1348100400016 
117.        0.204      0.006                                      1348100400017 
118.        0.196      0.006                                      1348100400018 
119.        0.213      0.006                                      1348100400019 
120.        0.228      0.006                                      1348100400020 
122.        0.254      0.005                                      1348100400021 
124.        0.427      0.009                                      1348100400022 
ENDDATA              8          0                                 1348100400023 
ENDSUBENT           22          0                                 1348100499999 
ENDENTRY             4          0                                 1348199999999