ENTRY            21723   20161001                             22532172300000001 
SUBENT        21723001   20161001                             22532172300100001 
BIB                 11         32                                 2172300100002 
INSTITUTE  (2SWTWUR) Eidgenoessisches Institut fuer Reaktor-      2172300100003 
            Forschung.                                            2172300100004 
REFERENCE  (J,NSE,79,167,198110) - final publ.                    2172300100005 
           ((P,NEANDC(OR)-154,12,1980)=(P,INDC(SWT)-14,12,1980))  2172300100006 
                                  Abstract,data for Mo-99,Te-132. 2172300100007 
REL-REF    (R,,J.K.Dickens+,J,NIM,175,535,1980) - decay-data      2172300100008 
                                                  of Mo-99        2172300100009 
           (R,,J.K.Dickens+,J,NSE,73,42,1980) - decay-data of     2172300100010 
                             Sr-92, Y-93, Zr-97, Ba-139, Ba-140   2172300100011 
           (R,,U.Reus+,R,GSI-79-2,1979) - decay-data of the rest  2172300100012 
                                          of the products         2172300100013 
            - G.Erdtmann and W.Soyka, 'Die gamma-Linien der       2172300100014 
            Radionuklide,' Chemie, Mannheim, New York (1979). -   2172300100015 
                                            decay-data of Cd-115m 2172300100016 
            - 'A Handbook of Radioactivity Measurement Procedures,2172300100017 
           NCRP Report No. 58, National Council on Radiation'     2172300100018 
           Protection and Measurements (1978). - decay-data of    2172300100019 
                                  Te-132, Ce-141, Ce-143, Sm-153  2172300100020 
AUTHOR     (H.N.Erten,A.Gruetter,E.Roessler,H.R.von Gunten)       2172300100021 
TITLE       Mass distribution in the reactor-neutron-induced      2172300100022 
            fission of thorium-232                                2172300100023 
FACILITY   (REAC,2SWTWUR) Swimming pool reactor SAPHIR.           2172300100024 
INC-SOURCE (REAC)                                                 2172300100025 
PART-DET   (DG) Decay gammas of the fission products.             2172300100026 
ADD-RES    (COMP) Comparison with literature both for reactor     2172300100027 
           neutron and monoenergetic neutron induced fission      2172300100028 
            of Th-232.                                            2172300100029 
CORRECTION .For Ag-113-m and Cd-115-m formation.                  2172300100030 
HISTORY    (19810119C) G.C.                                       2172300100031 
           (19811201A) T.N - 002 was changed and 003 was added.   2172300100032 
           (20161001A) SD:Updated to new date formats,lower case. 2172300100033 
           Entry re-compiled.                                     2172300100034 
ENDBIB              32          0                                 2172300100035 
COMMON               1          3                                 2172300100036 
EN-DUMMY                                                          2172300100037 
MEV                                                               2172300100038 
 3.3                                                              2172300100039 
ENDCOMMON            3          0                                 2172300100040 
ENDSUBENT           39          0                                 2172300199999 
SUBENT        21723002   20161001                             22532172300200001 
BIB                 13         42                                 2172300200002 
REACTION   (90-TH-232(N,F)ELEM/MASS,CUM,FY,,FIS)                  2172300200003 
MONITOR    ((MONIT)90-TH-232(N,F)42-MO-99,CUM,FY,,FIS)            2172300200004 
           (92-U-235(N,F)ELEM/MASS,CUM,FY,,FIS)                   2172300200005 
MONIT-REF  (,B.F.Rider,R,NEDO-12154-3B,1980)-The thermal-neutron  2172300200006 
            -induced fission yields of U-238 used in the R method 2172300200007 
INC-SPECT  Fission neutron spectrum. The thermal neutron flux was 2172300200008 
           ~1.6 x 10**13 n/cm2/s and the fast neutron flux was    2172300200009 
           ~3.3 x 10**12 ncm2/s.                                  2172300200010 
SAMPLE     .Th-232 100%, Th(NO3)4.x H2O, 50 mg                    2172300200011 
           .U-235, 99.61%, UO2(NO3)2, 14.4 mu-g.                  2172300200012 
            The sources were wrapped in thin (~4 mg/cm2) aluminum 2172300200013 
            foils and were placed in quartz tubes.                2172300200014 
            Samples were irradiated simultaneously, but in        2172300200015 
           separated positions, in the SAPHIR reactor for 1 h.    2172300200016 
METHOD     (CHSEP) Radiochemical separation of the fission        2172300200017 
            products from Th-232(n,f) and U-235(n,f). The         2172300200018 
            quantity                                              2172300200019 
                    R=Ast(Th)*A2/(Ast(U)*A4) is measured, were    2172300200020 
                    Ast(Th)= activity of product in Th-232(n,f),  2172300200021 
                    A2= activity of Mo-99 in U-235(n,f),          2172300200022 
                    Ast(U)= activity of product  in U-235(n,f),   2172300200023 
                     compilation by Rider(NEDO 12154-3B) was used.2172300200024 
                    A4= activity of Mo-99 in Th-232(n,f).         2172300200025 
           The yields in thorium fission were then determined     2172300200026 
           according to Yi(Th) = R*Yi(U)*Yst(Th)/Yst(U)           2172300200027 
           (GSPEC) gamma-ray spectroscopy.                        2172300200028 
DETECTOR   (GELI ) Ge(Li) detectors. 45 cm3 and 54 cm3.           2172300200029 
            Resolution about 2 keV at 1332 keV.                   2172300200030 
           (PROPC) Low background proportional counter for Sc-89, 2172300200031 
           Y-90, and RU-106 counting.                             2172300200032 
ANALYSIS    Gaussian peak fit and decay analysis.                 2172300200033 
ERR-ANALYS (ERR-T) Total error given, including the statistical   2172300200034 
            error, the errors in the U-235 reference yields  and  2172300200035 
           (MONIT-ERR) Normalization uncertainty                  2172300200036 
MISC-COL   (MISC1) R-value Y1*Y2/(Y3-Y4) measured.                2172300200037 
           (MISC2) Number of determinations.                      2172300200038 
FLAG       (1.) Values based on R-method are omitted.             2172300200039 
           (2.) Determined by beta counting.                      2172300200040 
           (3.) Determined by direct gamma-ray spectroscopy.      2172300200041 
STATUS     (TABLE) Data taken from Tbl.III,IV of NSE,79,167,1981  2172300200042 
           (DEP,21723004) data for normalization                  2172300200043 
HISTORY    (20161001A) SD: BIB update.                            2172300200044 
ENDBIB              42          0                                 2172300200045 
COMMON               4          3                                 2172300200046 
ELEM-NRM   MASS-NRM   MONIT      MONIT-ERR                        2172300200047 
NO-DIM     NO-DIM     PC/FIS     PC/FIS                           2172300200048 
        42.        99.       2.98       0.15                      2172300200049 
ENDCOMMON            3          0                                 2172300200050 
DATA                 9         36                                 2172300200051 
ELEMENT    MASS       ISOMER     DATA       ERR-T      MISC1      2172300200052 
MISC1-ERR  MISC2      FLAG                                        2172300200053 
NO-DIM     NO-DIM     NO-DIM     PC/FIS     PC/FIS     NO-DIM     2172300200054 
NO-DIM     NO-DIM     NO-DIM                                      2172300200055 
        32.        77.         0.     0.0113     0.0017           2172300200056 
                    4.         1.                                 2172300200057 
        32.        78.                 0.073      0.011           2172300200058 
                    4.         1.                                 2172300200059 
        35.        83.                  2.13       0.20       8.092172300200060 
       0.61         3.                                            2172300200061 
        35.        84.                  3.84       0.31       8.192172300200062 
       0.64         3.                                            2172300200063 
        38.        89.                  7.50       0.54       3.172172300200064 
       0.15         5.         2.                                 2172300200065 
        38.        90.                  8.21       0.79        2.92172300200066 
       0.23         2.         2.                                 2172300200067 
        38.        91.                  7.59       0.42       2.612172300200068 
       0.03         3.                                            2172300200069 
        38.        92.                  6.80       0.41       2.352172300200070 
       0.05         3.                                            2172300200071 
        39.        93.                  6.76       0.54       2.162172300200072 
       0.03         2.                                            2172300200073 
        40.        95.                  5.63       0.31       1.762172300200074 
       0.02         2.         3.                                 2172300200075 
        40.        97.                  4.50       0.35       1.552172300200076 
       0.08         2.         3.                                 2172300200077 
        44.       103.                 0.158      0.009      0.1062172300200078 
      0.002         4.                                            2172300200079 
        44.       105.                0.0561     0.0046      0.1182172300200080 
      0.002         4.                                            2172300200081 
        44.       106.                0.0487     0.0085      0.2472172300200082 
        0.4         3.         2.                                 2172300200083 
        46.       109.                0.0563     0.0096       3.482172300200084 
       0.08         5.                                            2172300200085 
        46.       112.                0.0774     0.0042      12.132172300200086 
       0.15         5.                                            2172300200087 
        47.       111.                0.0703     0.0056        7.52172300200088 
       0.15         5.                                            2172300200089 
        47.       113.         0.     0.0785     0.0079      11.682172300200090 
       0.35         5.                                            2172300200091 
        48.       115.         0.     0.0506     0.0061      11.212172300200092 
       0.11         5.                                            2172300200093 
        48.       117.         0.      0.050      0.012      12.972172300200094 
        0.2         5.                                            2172300200095 
        48.       117.         1.     0.0227     0.0053       10.32172300200096 
       0.46         5.                                            2172300200097 
        51.       127.                0.0809     0.0078       1.322172300200098 
       0.02         4.                                            2172300200099 
        51.       129.                 0.310      0.025      0.8432172300200100 
      0.008         4.                                            2172300200101 
        52.       132.                  3.16       0.17        1.52172300200102 
       0.02        13.                                            2172300200103 
        53.       131.                  1.80       0.10       1.272172300200104 
       0.02         3.                                            2172300200105 
        53.       134.         0.       6.23       0.56       1.632172300200106 
       0.07         3.                                            2172300200107 
        53.       135.                  6.14       0.36       1.992172300200108 
       0.03         3.                                            2172300200109 
        56.       139.                  7.11       0.42       2.282172300200110 
       0.05         3.                                            2172300200111 
        56.       140.                  8.12       0.45       2.672172300200112 
       0.03         3.                                            2172300200113 
        58.       141.                  7.36       0.47       2.592172300200114 
       0.09         4.                                            2172300200115 
        58.       143.                  6.96       0.46       2.382172300200116 
       0.09         4.                                            2172300200117 
        58.       144.                  7.79       0.49       2.962172300200118 
       0.09         4.                                            2172300200119 
        60.       147.                  3.05       0.20       2.742172300200120 
       0.11         4.                                            2172300200121 
        61.       149.                  1.16       0.07       2.182172300200122 
       0.06         4.                                            2172300200123 
        61.       151.                 0.396       0.03       1.922172300200124 
        0.1         4.                                            2172300200125 
        62.       153.                 0.106      0.012       1.332172300200126 
       0.13         3.                                            2172300200127 
ENDDATA             76          0                                 2172300200128 
ENDSUBENT          127          0                                 2172300299999 
SUBENT        21723003   20161001                             22532172300300001 
BIB                  4          6                                 2172300300002 
REACTION   (90-TH-232(N,F)48-CD-117,CUM,FY,,FIS)                  2172300300003 
MISC-COL   (MISC ) Number of determinations.                      2172300300004 
ERR-ANALYS (ERR-T) Total error. See description in Subent 002 and 2172300300005 
            STATUS in Subent 003.                                 2172300300006 
STATUS     (TABLE) Data taken from Tbl.III of NSE,79,167,1981     2172300300007 
           (DEP,21723002) Sum of values for Cd-117g and Cd-117m.  2172300300008 
ENDBIB               6          0                                 2172300300009 
NOCOMMON             0          0                                 2172300300010 
DATA                 5          1                                 2172300300011 
ELEMENT    MASS       DATA       ERR-T      MISC                  2172300300012 
NO-DIM     NO-DIM     PC/FIS     PC/FIS     NO-DIM                2172300300013 
        48.       117.      0.073      0.017         5.           2172300300014 
ENDDATA              3          0                                 2172300300015 
ENDSUBENT           14          0                                 2172300399999 
SUBENT        21723004   20161001                             22532172300400001 
BIB                 12         26                                 2172300400002 
REACTION   (90-TH-232(N,F)ELEM/MASS,IND,FY,,FIS)                  2172300400003 
DECAY-DATA (42-MO-99,66.0HR,DG)                                   2172300400004 
           (52-TE-132,78.2HR,DG)                                  2172300400005 
INC-SPECT  Fission neutrons. The irradiations lasted for ~70 h    2172300400006 
           and the fission rate amounted to ~1400 fiss/s.         2172300400007 
SAMPLE      Uniformly electroplated deposits of 6 cm diameter,    2172300400008 
            containing about 15 mg of Th-232                      2172300400009 
METHOD     (CHSEP) The number of fissions is directly counted,    2172300400010 
            Mo and Te are chemically separated and gamma-counted. 2172300400011 
DETECTOR   (FISCH) Aluminium parallel plate type fission counter, 2172300400012 
           (GELI) Ge(Li)-detectors, 45 cm3, resolution about      2172300400013 
            2 keV at 1332 keV , and 54 cm3, resolution about      2172300400014 
            2 keV at 1332. keV.                                   2172300400015 
ANALYSIS   .Gaussian peak fit and decay analysis.                 2172300400016 
COMMENT    .Comparison with literature values.                    2172300400017 
ERR-ANALYS (ERR-T) Total error given. It includes -               2172300400018 
           (ERR-S) statistical error                              2172300400019 
             in fission fragment counting = 1%                    2172300400020 
             in activity measurements     = 2%                    2172300400021 
             in chemical yields           = 3%                    2172300400022 
              value in common section was estimated by compiler.  2172300400023 
           (ERR-SYS) The total systematic error is 4% from uncer- 2172300400024 
           tainties in decay schemes and detector efficiencies.   2172300400025 
MISC-COL   (MISC) Number of experiments done.                     2172300400026 
STATUS     (TABLE) Data taken from from Tbl.I of NSE,79,167,1981  2172300400027 
HISTORY    (20161001T) SD: Subent was added from 21712.002.       2172300400028 
ENDBIB              26          0                                 2172300400029 
COMMON               3          3                                 2172300400030 
ERR-S      ERR-SYS    MISC                                        2172300400031 
PER-CENT   PER-CENT   NO-DIM                                      2172300400032 
    3.7        4.       10.                                       2172300400033 
ENDCOMMON            3          0                                 2172300400034 
DATA                 4          2                                 2172300400035 
ELEMENT    MASS       DATA       ERR-T                            2172300400036 
NO-DIM     NO-DIM     PC/FIS     PC/FIS                           2172300400037 
        42.        99.       2.98       0.15                      2172300400038 
        52.       132.       2.76       0.16                      2172300400039 
ENDDATA              4          0                                 2172300400040 
ENDSUBENT           39          0                                 2172300499999 
ENDENTRY             4          0                                 2172399999999