ENTRY            20317   19860411                             00002031700000001 
SUBENT        20317001   19860411                             00002031700100001 
BIB                 13         39                                 2031700100002 
INSTITUTE  (2JPNKTO)                                              2031700100003 
REFERENCE  (J,NST,8,59,7102)                                      2031700100004 
           (R,EUR-5667,(2),142,75) REVIEW WITH SAME DATA.         2031700100005 
           (C,71VIENNA,,113,7108) FISSION PLATE DATA.             2031700100006 
           (P,EANDC(J)-19L,26,7008) ABST. SUPERSEDED.             2031700100007 
           (P,EANDC(J)-13L,23,6908) ABST. SUPERSEDED.             2031700100008 
AUTHOR     (I.KIMURA, K.KOBAYASHI, T.SHIBATA)                     2031700100009 
TITLE      -MEASUREMENTS OF AVERAGE CROSS SECTIONS FOR SOME       2031700100010 
            THRESHOLD REACTIONS FOR NEUTRONS WITH FISSION-TYPE    2031700100011 
            REACTOR SPECTRUM-                                     2031700100012 
FACILITY   (REAC ) KYOTO UNIVERSITY RESEARCH REACTOR, KUR.        2031700100013 
            5 MEGA-WATT, THERMAL REACTOR. NEUTRON SPECTRUM        2031700100014 
            ABOVE 1.5 MEV IS VERY CLOSE TO A FISSION NEUTRON      2031700100015 
            SPECTRUM. THERE ARE HOWEVER MANY THERMAL NEUTRONS.    2031700100016 
INC-SPECT  .U-235 FISSION NEUTRON SPECTRUM.                       2031700100017 
METHOD     (ACTIV)    ACTIVATION.                                 2031700100018 
DETECTOR   (GELI )    GE(LI) CALIBRATED BY IAEA STANDARD SOURCES. 2031700100019 
MONITOR    ((MONIT1)13-AL-27(N,A)11-NA-24,,SIG,,FIS)              2031700100020 
           ((MONIT2)28-NI-58(N,P)27-CO-58,,SIG,,FIS)              2031700100021 
            THE VALUES OF THE FAST NEUTRON FLUX                   2031700100022 
            MEASURED WITH THESE MONITORS AGREE                    2031700100023 
            WITH EACH OTHER WITHIN 3 PERCENT FOR THE              2031700100024 
            FISSION SPECTRUM (FISSION PLATE) AND                  2031700100025 
            WITHIN 2 PERCENT FOR THE FAST REACTOR                 2031700100026 
            SPECTRUM.                                             2031700100027 
DECAY-MON  (11-NA-24-G,15.HR,DG,1370.,1.0)                        2031700100028 
           (27-CO-58-G,71.3D,DG,810.,0.99)                        2031700100029 
STATUS     .DATA FROM NUCL.SCI.TECHN.8,59.                        2031700100030 
HISTORY    (711010C)                                              2031700100031 
           (740626E)                                              2031700100032 
           (800722A) NEW REFERENCE AND FACILITY ADDED.            2031700100033 
           (800808E)                                              2031700100034 
           (840106U) A.P.T. JAPAN CODE CHANGED TO JPN             2031700100035 
           (840106E)                                              2031700100036 
           (860227A)N.CH                                          2031700100037 
           (860411E)                                              2031700100038 
ERR-ANALYS .STATISTICAL ERROR, UNCERTAINTY IN MONITORING THE      2031700100039 
            NEUTRON FLUX, SYSTEMATIC ERROR ABOUT 5 PERCENT.       2031700100040 
           .DETAILED DISCUSSION IN REFERENCE.                     2031700100041 
ENDBIB              39          0                                 2031700100042 
COMMON               3          3                                 2031700100043 
EN-DUMMY   MONIT1     MONIT2                                      2031700100044 
MEV        MB         MB                                          2031700100045 
 1.5000E+00 6.4400E-01 1.0200E+02                                 2031700100046 
ENDCOMMON            3          0                                 2031700100047 
ENDSUBENT           46          0                                 2031700199999 
SUBENT        20317002   19831122                             00002031700200001 
BIB                  5          9                                 2031700200002 
REACTION   (14-SI-28(N,P)13-AL-28,,SIG,,FIS)                      2031700200003 
INC-SOURCE (REAC )    KUR-REACTOR, FISSION TYPE SPECTRUM.         2031700200004 
SAMPLE     .SI-SQUARE PLATES 8 MILLIM. X 8 MILLIM. X              2031700200005 
            0.2 MILLIM, P-TYPE SINGLE CRYSTAL.                    2031700200006 
DECAY-DATA (13-AL-28,2.24MIN,DG)                                  2031700200007 
HISTORY    (711010C)                                              2031700200008 
           (740626E)                                              2031700200009 
           (800722A) REACTION RE-DEFINED.                         2031700200010 
           (800808E)                                              2031700200011 
ENDBIB               9          0                                 2031700200012 
NOCOMMON             0          0                                 2031700200013 
DATA                 2          1                                 2031700200014 
DATA       DATA-ERR                                               2031700200015 
MB         MB                                                     2031700200016 
 4.9000E+00 3.2000E-01                                            2031700200017 
ENDDATA              3          0                                 2031700200018 
ENDSUBENT           17          0                                 2031700299999 
SUBENT        20317003   19831122                             00002031700300001 
BIB                  5          9                                 2031700300002 
REACTION   (14-SI-29(N,P)13-AL-29,,SIG,,FIS)                      2031700300003 
INC-SOURCE (REAC )    KUR-REACTOR, FISSION TYPE SPECTRUM.         2031700300004 
SAMPLE     .SI-SQUARE PLATES 8 MILLIM. X 8 MILLIM. X              2031700300005 
            0.2 MILLIM, P-TYPE SINGLE CRYSTAL.                    2031700300006 
DECAY-DATA (13-AL-29,6.6MIN,DG)                                   2031700300007 
HISTORY    (711010C)                                              2031700300008 
           (740626E)                                              2031700300009 
           (800722A) REACTION RE-DEFINED.                         2031700300010 
           (800808E)                                              2031700300011 
ENDBIB               9          0                                 2031700300012 
NOCOMMON             0          0                                 2031700300013 
DATA                 2          1                                 2031700300014 
DATA       DATA-ERR                                               2031700300015 
MB         MB                                                     2031700300016 
 2.9800E+00 1.7000E-01                                            2031700300017 
ENDDATA              3          0                                 2031700300018 
ENDSUBENT           17          0                                 2031700399999 
SUBENT        20317004   19831122                             00002031700400001 
BIB                  5          9                                 2031700400002 
REACTION   (14-SI-30(N,A)12-MG-27,,SIG,,FIS)                      2031700400003 
INC-SOURCE (REAC )    KUR-REACTOR, FISSION TYPE SPECTRUM.         2031700400004 
SAMPLE     .SI-SQUARE PLATES 8 MILLIM. X 8 MILLIM. X              2031700400005 
            0.2 MILLIM, P-TYPE SINGLE CRYSTAL.                    2031700400006 
DECAY-DATA (12-MG-27,9.46MIN,DG)                                  2031700400007 
HISTORY    (711010C)                                              2031700400008 
           (740626E)                                              2031700400009 
           (800722A) REACTION RE-DEFINED.                         2031700400010 
           (800808E)                                              2031700400011 
ENDBIB               9          0                                 2031700400012 
NOCOMMON             0          0                                 2031700400013 
DATA                 2          1                                 2031700400014 
DATA       DATA-ERR                                               2031700400015 
MB         MB                                                     2031700400016 
 1.3000E-01 2.0000E-02                                            2031700400017 
ENDDATA              3          0                                 2031700400018 
ENDSUBENT           17          0                                 2031700499999 
SUBENT        20317005   19831122                             00002031700500001 
BIB                  6         10                                 2031700500002 
REACTION   (22-TI-46(N,P)21-SC-46-G,,SIG,,FIS)                    2031700500003 
INC-SOURCE (REAC )    KUR-REACTOR, FISSION TYPE SPECTRUM.         2031700500004 
SAMPLE      99.73 PERCENT PURE TI-FOILS, 0.5 INCH DIAM.,          2031700500005 
            0.01 INCH THICK.                                      2031700500006 
DECAY-DATA (21-SC-46-G,83.9D,DG,890.,,DG,1120.)                   2031700500007 
COMMENT     83.9 DAYS HL      E ACTIVITY MEASURED.                2031700500008 
HISTORY    (711010C)                                              2031700500009 
           (740626E)                                              2031700500010 
           (800722A) REACTION RE-DEFINED.                         2031700500011 
           (800808E)                                              2031700500012 
ENDBIB              10          0                                 2031700500013 
NOCOMMON             0          0                                 2031700500014 
DATA                 2          1                                 2031700500015 
DATA       DATA-ERR                                               2031700500016 
MB         MB                                                     2031700500017 
 1.1200E+01 6.3000E-01                                            2031700500018 
ENDDATA              3          0                                 2031700500019 
ENDSUBENT           18          0                                 2031700599999 
SUBENT        20317006   19831122                             00002031700600001 
BIB                  6         12                                 2031700600002 
REACTION   (22-TI-46(N,P)21-SC-46-G,,SIG,,FIS)                    2031700600003 
INC-SOURCE (REAC )    NEUTRONS FROM ENRICHED U-235 PLATE PLACED   2031700600004 
            IN THE THERMAL NEUTRON IRRADIATION FACILITY           2031700600005 
            OF KUR-REACTOR.                                       2031700600006 
SAMPLE      99.73 PERCENT PURE TI-FOILS, 0.5 INCH DIAM.,          2031700600007 
            0.01 INCH THICK.                                      2031700600008 
DECAY-DATA (21-SC-46-G,83.9D,DG,890.,,DG,1120.)                   2031700600009 
COMMENT     83.9 DAYS HL      E ACTIVITY MEASURED.                2031700600010 
HISTORY    (711010C)                                              2031700600011 
           (740626E)                                              2031700600012 
           (800721A) REACTION RE-DEFINED.                         2031700600013 
           (800808E)                                              2031700600014 
ENDBIB              12          0                                 2031700600015 
NOCOMMON             0          0                                 2031700600016 
DATA                 2          1                                 2031700600017 
DATA       DATA-ERR                                               2031700600018 
MB         MB                                                     2031700600019 
 1.0800E+01 6.1000E-01                                            2031700600020 
ENDDATA              3          0                                 2031700600021 
ENDSUBENT           20          0                                 2031700699999 
SUBENT        20317007   19831122                             00002031700700001 
BIB                  5          9                                 2031700700002 
REACTION   (22-TI-47(N,P)21-SC-47,,SIG,,FIS)                      2031700700003 
INC-SOURCE (REAC )    KUR-REACTOR, FISSION TYPE SPECTRUM.         2031700700004 
SAMPLE      99.73 PERCENT PURE TI-FOILS, 0.5 INCH DIAM.,          2031700700005 
            0.01 INCH THICK.                                      2031700700006 
DECAY-DATA (21-SC-47,3.42D,DG,160.)                               2031700700007 
HISTORY    (711010C)                                              2031700700008 
           (740626E)                                              2031700700009 
           (800722A) REACTION RE-DEFINED.                         2031700700010 
           (800808E)                                              2031700700011 
ENDBIB               9          0                                 2031700700012 
NOCOMMON             0          0                                 2031700700013 
DATA                 2          1                                 2031700700014 
DATA       DATA-ERR                                               2031700700015 
MB         MB                                                     2031700700016 
 1.9000E+01 1.2000E+00                                            2031700700017 
ENDDATA              3          0                                 2031700700018 
ENDSUBENT           17          0                                 2031700799999 
SUBENT        20317008   19831122                             00002031700800001 
BIB                  5         11                                 2031700800002 
REACTION   (22-TI-47(N,P)21-SC-47,,SIG,,FIS)                      2031700800003 
INC-SOURCE (REAC )    NEUTRONS FROM ENRICHED U-235 PLATE PLACED   2031700800004 
            IN THE THERMAL NEUTRON IRRADIATION FACILITY           2031700800005 
            OF KUR-REACTOR.                                       2031700800006 
SAMPLE      99.73 PERCENT PURE TI-FOILS, 0.5 INCH DIAM.,          2031700800007 
            0.01 INCH THICK.                                      2031700800008 
DECAY-DATA (21-SC-47,3.42D,DG,160.)                               2031700800009 
HISTORY    (711010C)                                              2031700800010 
           (740626E)                                              2031700800011 
           (800722A) REACTION RE-DEFINED.                         2031700800012 
           (800808E)                                              2031700800013 
ENDBIB              11          0                                 2031700800014 
NOCOMMON             0          0                                 2031700800015 
DATA                 2          1                                 2031700800016 
DATA       DATA-ERR                                               2031700800017 
MB         MB                                                     2031700800018 
 1.7300E+01 9.0000E-01                                            2031700800019 
ENDDATA              3          0                                 2031700800020 
ENDSUBENT           19          0                                 2031700899999 
SUBENT        20317009   19831122                             00002031700900001 
BIB                  5          9                                 2031700900002 
REACTION   (22-TI-48(N,P)21-SC-48,,SIG,,FIS)                      2031700900003 
INC-SOURCE (REAC )    KUR-REACTOR, FISSION TYPE SPECTRUM.         2031700900004 
SAMPLE      99.73 PERCENT PURE TI-FOILS, 0.5 INCH DIAM.,          2031700900005 
            0.01 INCH THICK.                                      2031700900006 
DECAY-DATA (21-SC-48,43.7HR,DG,980.,,DG,1040.,,DG,1314.)          2031700900007 
HISTORY    (711010C)                                              2031700900008 
           (740626E)                                              2031700900009 
           (800722A) REACTION RE-DEFINED.                         2031700900010 
           (800808E)                                              2031700900011 
ENDBIB               9          0                                 2031700900012 
NOCOMMON             0          0                                 2031700900013 
DATA                 2          1                                 2031700900014 
DATA       DATA-ERR                                               2031700900015 
MB         MB                                                     2031700900016 
 2.9400E-01 2.5000E-02                                            2031700900017 
ENDDATA              3          0                                 2031700900018 
ENDSUBENT           17          0                                 2031700999999 
SUBENT        20317010   19831122                             00002031701000001 
BIB                  5         11                                 2031701000002 
REACTION   (22-TI-48(N,P)21-SC-48,,SIG,,FIS)                      2031701000003 
INC-SOURCE (REAC )    NEUTRONS FROM ENRICHED U-235 PLATE PLACED   2031701000004 
            IN THE THERMAL NEUTRON IRRADIATION FACILITY           2031701000005 
            OF KUR-REACTOR.                                       2031701000006 
SAMPLE      99.73 PERCENT PURE TI-FOILS, 0.5 INCH DIAM.,          2031701000007 
            0.01 INCH THICK.                                      2031701000008 
DECAY-DATA (21-SC-48,43.7HR,DG,980.,,DG,1040.,,DG,1314.)          2031701000009 
HISTORY    (711010C)                                              2031701000010 
           (740626E)                                              2031701000011 
           (800722A) REACTION RE-DEFINED.                         2031701000012 
           (800808E)                                              2031701000013 
ENDBIB              11          0                                 2031701000014 
NOCOMMON             0          0                                 2031701000015 
DATA                 2          1                                 2031701000016 
DATA       DATA-ERR                                               2031701000017 
MB         MB                                                     2031701000018 
 2.7200E-01 1.6000E-02                                            2031701000019 
ENDDATA              3          0                                 2031701000020 
ENDSUBENT           19          0                                 2031701099999 
SUBENT        20317011   19831122                             00002031701100001 
BIB                  5          9                                 2031701100002 
REACTION   (23-V-51(N,A)21-SC-48,,SIG,,FIS)                       2031701100003 
INC-SOURCE (REAC )    KUR-REACTOR, FISSION TYPE SPECTRUM.         2031701100004 
SAMPLE      99.72 PERCENT PURE V-FOILS, 0.5 INCH DIAM.,           2031701100005 
            0.003 INCH THICK.                                     2031701100006 
DECAY-DATA (21-SC-48,43.7HR,DG,980.,,DG,1040.,,DG,1314.)          2031701100007 
HISTORY    (711010C)                                              2031701100008 
           (740626E)                                              2031701100009 
           (800722A) REACTION RE-DEFINED.                         2031701100010 
           (800808E)                                              2031701100011 
ENDBIB               9          0                                 2031701100012 
NOCOMMON             0          0                                 2031701100013 
DATA                 2          1                                 2031701100014 
DATA       DATA-ERR                                               2031701100015 
MB         MB                                                     2031701100016 
 2.1700E-02 1.5000E-03                                            2031701100017 
ENDDATA              3          0                                 2031701100018 
ENDSUBENT           17          0                                 2031701199999 
SUBENT        20317012   19831122                             00002031701200001 
BIB                  4          7                                 2031701200002 
REACTION   (30-ZN-64(N,P)29-CU-64,,SIG,,FIS)                      2031701200003 
INC-SOURCE (REAC )    KUR-REACTOR, FISSION TYPE SPECTRUM.         2031701200004 
DECAY-DATA (29-CU-64,12.7HR,DG)                                   2031701200005 
HISTORY    (711010C)                                              2031701200006 
           (740626E)                                              2031701200007 
           (800722A) REACTION RE-DEFINED.                         2031701200008 
           (800808E)                                              2031701200009 
ENDBIB               7          0                                 2031701200010 
NOCOMMON             0          0                                 2031701200011 
DATA                 2          1                                 2031701200012 
DATA       DATA-ERR                                               2031701200013 
MB         MB                                                     2031701200014 
 3.5500E+01 2.8000E+00                                            2031701200015 
ENDDATA              3          0                                 2031701200016 
ENDSUBENT           15          0                                 2031701299999 
SUBENT        20317013   19831122                             00002031701300001 
BIB                  4          9                                 2031701300002 
REACTION   (30-ZN-64(N,P)29-CU-64,,SIG,,FIS)                      2031701300003 
INC-SOURCE (REAC )    NEUTRONS FROM ENRICHED U-235 PLATE PLACED   2031701300004 
            IN THE THERMAL NEUTRON IRRADIATION FACILITY           2031701300005 
            OF KUR-REACTOR.                                       2031701300006 
DECAY-DATA (29-CU-64,12.7HR,DG)                                   2031701300007 
HISTORY    (711010C)                                              2031701300008 
           (740626E)                                              2031701300009 
           (800722A) REACTION RE-DEFINED.                         2031701300010 
           (800808E)                                              2031701300011 
ENDBIB               9          0                                 2031701300012 
NOCOMMON             0          0                                 2031701300013 
DATA                 2          1                                 2031701300014 
DATA       DATA-ERR                                               2031701300015 
MB         MB                                                     2031701300016 
 3.7400E+01 3.0000E+00                                            2031701300017 
ENDDATA              3          0                                 2031701300018 
ENDSUBENT           17          0                                 2031701399999 
SUBENT        20317014   19831122                             00002031701400001 
BIB                  6         10                                 2031701400002 
REACTION   (41-NB-93(N,2N)41-NB-92-M,,SIG,,FIS)                   2031701400003 
INC-SOURCE (REAC )    KUR-REACTOR, FISSION TYPE SPECTRUM.         2031701400004 
SAMPLE      99.84 PERCENT PURE NB-FOILS, 0.5 INCH DIAM.,          2031701400005 
            0.005 INCH THICK.                                     2031701400006 
DECAY-DATA (41-NB-92-M,10.16D,DG)                                 2031701400007 
COMMENT     10.16 DAYS HALF-LIFE ACTIVITY MEASURED.               2031701400008 
HISTORY    (711010C)                                              2031701400009 
           (740626E)                                              2031701400010 
           (800722A) REACTION RE-DEFINED.                         2031701400011 
           (800808E)                                              2031701400012 
ENDBIB              10          0                                 2031701400013 
NOCOMMON             0          0                                 2031701400014 
DATA                 2          1                                 2031701400015 
DATA       DATA-ERR                                               2031701400016 
MB         MB                                                     2031701400017 
 4.3200E-01 3.3000E-02                                            2031701400018 
ENDDATA              3          0                                 2031701400019 
ENDSUBENT           18          0                                 2031701499999 
SUBENT        20317015   19831122                             00002031701500001 
BIB                  6         12                                 2031701500002 
REACTION   (41-NB-93(N,2N)41-NB-92-M,,SIG,,FIS)                   2031701500003 
INC-SOURCE (REAC )    NEUTRONS FROM ENRICHED U-235 PLATE PLACED   2031701500004 
            IN THE THERMAL NEUTRON IRRADIATION FACILITY           2031701500005 
            OF KUR-REACTOR.                                       2031701500006 
SAMPLE      99.84 PERCENT PURE NB-FOILS, 0.5 INCH DIAM.,          2031701500007 
            0.005 INCH THICK.                                     2031701500008 
DECAY-DATA (41-NB-92-M,10.16D,DG)                                 2031701500009 
COMMENT     10.16 DAYS HALF-LIFE ACTIVITY MEASURED.               2031701500010 
HISTORY    (711010C)                                              2031701500011 
           (740626E)                                              2031701500012 
           (800722A) REACTION RE-DEFINED.                         2031701500013 
           (800808E)                                              2031701500014 
ENDBIB              12          0                                 2031701500015 
NOCOMMON             0          0                                 2031701500016 
DATA                 2          1                                 2031701500017 
DATA       DATA-ERR                                               2031701500018 
MB         MB                                                     2031701500019 
 4.0200E-01 3.4000E-02                                            2031701500020 
ENDDATA              3          0                                 2031701500021 
ENDSUBENT           20          0                                 2031701599999 
SUBENT        20317016   19831122                             00002031701600001 
BIB                  6         10                                 2031701600002 
REACTION   (42-MO-92(N,P)41-NB-92-M,,SIG,,FIS)                    2031701600003 
INC-SOURCE (REAC )    KUR-REACTOR, FISSION TYPE SPECTRUM.         2031701600004 
SAMPLE      99.92 PERCENT PURE FOILS, 0.5 INCH DIAM.,             2031701600005 
            0.003 INCH THICK.                                     2031701600006 
DECAY-DATA (41-NB-92-M,10.16D,DG)                                 2031701600007 
COMMENT     10.16 DAYS HALF-LIFE ACTIVITY MEASURED.               2031701600008 
HISTORY    (711010C)                                              2031701600009 
           (740626E)                                              2031701600010 
           (800722A) REACTION RE-DEFINED.                         2031701600011 
           (800808E)                                              2031701600012 
ENDBIB              10          0                                 2031701600013 
NOCOMMON             0          0                                 2031701600014 
DATA                 2          1                                 2031701600015 
DATA       DATA-ERR                                               2031701600016 
MB         MB                                                     2031701600017 
 6.0000E+00 4.3000E-01                                            2031701600018 
ENDDATA              3          0                                 2031701600019 
ENDSUBENT           18          0                                 2031701699999 
SUBENT        20317017   19831122                             00002031701700001 
BIB                  6         12                                 2031701700002 
REACTION   (42-MO-92(N,P)41-NB-92-M,,SIG,,FIS)                    2031701700003 
INC-SOURCE (REAC )    NEUTRONS FROM ENRICHED U-235 PLATE PLACED   2031701700004 
            IN THE THERMAL NEUTRON IRRADIATION FACILITY           2031701700005 
            OF KUR REACTOR.                                       2031701700006 
SAMPLE      99.92 PERCENT PURE FOILS, 0.5 INCH DIAM.,             2031701700007 
            0.003 INCH THICK.                                     2031701700008 
DECAY-DATA (41-NB-92-M,10.16D,DG)                                 2031701700009 
COMMENT     10.16 DAYS HALF-LIFE ACTIVITY MEASURED.               2031701700010 
HISTORY    (711010C)                                              2031701700011 
           (740626E)                                              2031701700012 
           (800722A) REACTION RE-DEFINED.                         2031701700013 
           (800808E)                                              2031701700014 
ENDBIB              12          0                                 2031701700015 
NOCOMMON             0          0                                 2031701700016 
DATA                 2          1                                 2031701700017 
DATA       DATA-ERR                                               2031701700018 
MB         MB                                                     2031701700019 
 6.0400E+00 4.5000E-01                                            2031701700020 
ENDDATA              3          0                                 2031701700021 
ENDSUBENT           20          0                                 2031701799999 
SUBENT        20317018   19831122                             00002031701800001 
BIB                  6         17                                 2031701800002 
REACTION   (82-PB-204(N,INL)82-PB-204-M,,SIG,,FIS)                2031701800003 
INC-SOURCE (REAC )    KUR-REACTOR, FISSION TYPE SPECTRUM.         2031701800004 
SAMPLE      99.99 PERCENT PURE FOILS, 10 MILLIM. X                2031701800005 
            10 MILLIM. X 1 MILLIM.                                2031701800006 
DECAY-DATA (82-PB-204-M,67.0MIN,DG,375.,,DG,899.,,DG,912.)        2031701800007 
COMMENT    .THE CROSS-SECTION OBTAINED FROM THE 375 KEV GAMMAS    2031701800008 
            WERE ABOUT 10 PERCENT LOWER THAN THOSE OBTAINED       2031701800009 
            FROM THE 899, 912 KEV GAMMAS. THIS DISCREPANCY MIGHT  2031701800010 
            BE DUE TO AN ERROR IN THE DECAY SCHEME TAKEN FROM     2031701800011 
            THE TABLE BY C.M.LEDERER ET AL., TABLE OF ISOTOPES,   2031701800012 
            6-TH ED., 1968. THE AVERAGE CROSS-SECTION VALUE IS    2031701800013 
            GIVEN.                                                2031701800014 
            67 MIN, HALF-LIFE ACTIVITY MEASURED.                  2031701800015 
HISTORY    (711010C)                                              2031701800016 
           (740626E)                                              2031701800017 
           (800722A) REACTION RE-DEFINED.                         2031701800018 
           (800808E)                                              2031701800019 
ENDBIB              17          0                                 2031701800020 
NOCOMMON             0          0                                 2031701800021 
DATA                 2          1                                 2031701800022 
DATA       DATA-ERR                                               2031701800023 
MB         MB                                                     2031701800024 
 1.8900E+01 2.0000E+00                                            2031701800025 
ENDDATA              3          0                                 2031701800026 
ENDSUBENT           25          0                                 2031701899999 
SUBENT        20317019   19831122                             00002031701900001 
BIB                  6         10                                 2031701900002 
REACTION   (82-PB-204(N,2N)82-PB-203-G,,SIG,,FIS)                 2031701900003 
INC-SOURCE (REAC )    KUR-REACTOR, FISSION TYPE SPECTRUM.         2031701900004 
SAMPLE      99.99 PERCENT PURE FOILS, 10 MILLIM. X                2031701900005 
            10 MILLIM. X 1 MILLIM.                                2031701900006 
DECAY-DATA (82-PB-203-G,52.1HR,DG)                                2031701900007 
COMMENT     52.1 HOURS HALF-LIFE ACTIVITY MEASURED.               2031701900008 
HISTORY    (711010C)                                              2031701900009 
           (740626E)                                              2031701900010 
           (800722A) REACTION RE-DEFINED.                         2031701900011 
           (800808E)                                              2031701900012 
ENDBIB              10          0                                 2031701900013 
NOCOMMON             0          0                                 2031701900014 
DATA                 2          1                                 2031701900015 
DATA       DATA-ERR                                               2031701900016 
MB         MB                                                     2031701900017 
 1.9000E+00 1.8000E-01                                            2031701900018 
ENDDATA              3          0                                 2031701900019 
ENDSUBENT           18          0                                 2031701999999 
SUBENT        20317020   19831122                             00002031702000001 
BIB                  5          6                                 2031702000002 
REACTION   (13-AL-27(N,P)12-MG-27,,SIG,,FIS)                      2031702000003 
INC-SOURCE (REAC ) FISSION PLATE IN KUR REACTOR.                  2031702000004 
SAMPLE     .NO DETAILS.                                           2031702000005 
STATUS     .TABLE IN EUR-5667,142.                                2031702000006 
HISTORY    (800723C) SUBWORK ADDED.                               2031702000007 
           (800808E)                                              2031702000008 
ENDBIB               6          0                                 2031702000009 
NOCOMMON             0          0                                 2031702000010 
DATA                 2          1                                 2031702000011 
DATA       DATA-ERR                                               2031702000012 
MB         MB                                                     2031702000013 
 3.4000E+00 1.0000E-01                                            2031702000014 
ENDDATA              3          0                                 2031702000015 
ENDSUBENT           14          0                                 2031702099999 
ENDENTRY            20          0                                 2031799999999