ENTRY            22064   20230209                                 2206400000001 
SUBENT        22064001   20230209   20231011                      2206400100001 
BIB                 10         23                                 2206400100002 
TITLE       Mass yields of Am-241 thermal-neutron fission         2206400100003 
AUTHOR     (H.Nakahara,I.Fujiwara,H.Okamoto,N.Imanishi,           2206400100004 
            M.Ishibashi,T.Nishi)                                  2206400100005 
REFERENCE  (J,JIN,33,3239,1971)                                   2206400100006 
INSTITUTE  (2JPNKTO)                                              2206400100007 
FACILITY   (REAC,2JPNKTO) Kyoto University reactor.               2206400100008 
INC-SOURCE (REAC) Graphite thermal column.                        2206400100009 
INC-SPECT   Thermal neutron spectrum. Thermal neutron flux        2206400100010 
            2.0E+10 neutrons/cm2 sec. Cadmium ratio for Au        2206400100011 
            was 5000.                                             2206400100012 
DETECTOR   (GELI) A 20 cm3 GeLi detector was used for measuring   2206400100013 
            the fission product activities. The detector          2206400100014 
            was calibrated by IAEA standard sources of Am-241,    2206400100015 
            Co-57, Hg-203, Cs-137, Mn-54, Co-60, Y-88, and by     2206400100016 
            Ce-141, Cr-51 and K-42 whose absolute disintegration  2206400100017 
            rates were known.                                     2206400100018 
CORRECTION  No details given.                                     2206400100019 
HISTORY    (19871109C) N.O.                                       2206400100020 
           (19880808U) IF. Small corrections                      2206400100021 
           (19890130U) IF.                                        2206400100022 
           (19900829A) S.W. Flag and monitor clarified in Subent 32206400100023 
           (20230209A) SD: Updated to new date formats,lower case.2206400100024 
           Corrections in all Subents. Subent 004 added.          2206400100025 
ENDBIB              23          0                                 2206400100026 
COMMON               1          3                                 2206400100027 
EN-DUMMY                                                          2206400100028 
EV                                                                2206400100029 
 2.5300E-02                                                       2206400100030 
ENDCOMMON            3          0                                 2206400100031 
ENDSUBENT           30          0                                 2206400199999 
SUBENT        22064002   20230209   20231011                      2206400200001 
BIB                  9         35                                 2206400200002 
REACTION   (95-AM-241(N,F)ELEM/MASS,CUM,FY,,SPA)                  2206400200003 
FLAG       (1.) Both the Mo and Tc measurements result in yield   2206400200004 
                values for Mo-99, therefore the value is rather   2206400200005 
                an averaged value for Mo.                         2206400200006 
           (2.) Sum of the yields for 2 isomers                   2206400200007 
           (3.) Normalized to the yield 3.48% for Ce-143.         2206400200008 
DECAY-DATA (42-MO-99,67.HR,DG,140.,.88)                           2206400200009 
           (43-TC-99-M,6.HR,DG,140.,.913)                         2206400200010 
           (47-AG-111-G,7.5D,DG,342.,.06)                         2206400200011 
           (47-AG-113-G,5.3HR,DG,298.,.072)                       2206400200012 
           (48-CD-115-G,2.3D,DG,523.,.24)                         2206400200013 
           (48-CD-117-M,3.4HR,DG,1997.,.219)                      2206400200014 
           (48-CD-117-G,2.4HR,DG,1577.,.163)                      2206400200015 
           (51-SB-127,3.89D,DG,473.,.246)                         2206400200016 
           (51-SB-129-G,4.35HR,DG,813.,.62)                       2206400200017 
           (56-BA-139,83.MIN,DG,166.,.224)                        2206400200018 
           (56-BA-140,12.8D,DG,537.,.236)                         2206400200019 
           (58-CE-141,33.D,DG,145.,.50)                           2206400200020 
           (58-CE-143,33.HR,DG,293.,.426)                         2206400200021 
           (60-ND-147,11.1D,DG,91.,.287)                          2206400200022 
ASSUMED    (ASSUM,95-AM-241(N,F),,SIG,,SPA) Cross section taken   2206400200023 
            from BNL-325.                                         2206400200024 
METHOD      Absolute measurement of fission yields.               2206400200025 
           (CHSEP) Chemical separation and purification.          2206400200026 
SAMPLE     Targets were prepared by drying pure Am-241 nitrate    2206400200027 
            (1/400 Pu-239) on a 5.16 mg/cm2 Al foil,              2206400200028 
            carefully wrapped. Irradiation times 2 - 10 hours.    2206400200029 
            A thin Au foil (100 mg/cm2) was used for              2206400200030 
            monitoring the neutron flux.                          2206400200031 
ERR-ANALYS (DATA-ERR) The given errors include uncertainties      2206400200032 
            in the chemical yield determinations, gamma-          2206400200033 
            counting and in the neutron flux determinations.      2206400200034 
STATUS     (TABLE) Table 1 of J.Inorg.Nucl.Chem.,33(1971)3239     2206400200035 
HISTORY    (19880808U) If. Small corrections                      2206400200036 
           (20230209A) SD: BIB updated. MONITOR -> ASSUMED.       2206400200037 
ENDBIB              35          0                                 2206400200038 
COMMON               1          3                                 2206400200039 
ASSUM                                                             2206400200040 
B                                                                 2206400200041 
 3.13                                                             2206400200042 
ENDCOMMON            3          0                                 2206400200043 
DATA                 6         12                                 2206400200044 
ELEMENT    MASS       ISOMER     DATA       DATA-ERR   FLAG       2206400200045 
NO-DIM     NO-DIM     NO-DIM     PC/FIS     PC/FIS     NO-DIM     2206400200046 
        43.        99.              6.90E+00   2.60E-01         1.2206400200047 
        47.       111.              1.19E+00   4.00E-02           2206400200048 
        47.       113.         0.   4.87E-01   1.10E-02           2206400200049 
        48.       115.         0.   7.50E-02   8.00E-03           2206400200050 
        48.       117.              8.60E-03   2.10E-03         2.2206400200051 
        51.       127.              6.60E-01   3.00E-02           2206400200052 
        51.       129.              1.32E+00   5.00E-02           2206400200053 
        56.       139.              8.68E+00   2.70E-01           2206400200054 
        56.       140.              5.63E+00   1.10E-01           2206400200055 
        58.       141.              6.73E+00                    2.2206400200056 
        58.       143.              3.48E+00                    3.2206400200057 
        60.       147.              1.83E+00                    2.2206400200058 
ENDDATA             14          0                                 2206400200059 
ENDSUBENT           58          0                                 2206400299999 
SUBENT        22064003   20230209   20231011                      2206400300001 
BIB                  9         42                                 2206400300002 
REACTION   (95-AM-241(N,F)ELEM/MASS,CUM,FY,,SPA)                  2206400300003 
DECAY-DATA (38-SR-91,9.67HR,DG,750.,.29)                          2206400300004 
           (38-SR-92,2.7HR,DG,1383.,.90)                          2206400300005 
           (40-ZR-95,65.D,DG,724.,.49)                            2206400300006 
           (40-ZR-97,17.HR,DG,658.,.98)                           2206400300007 
           (41-NB-97-G,72.MIN,DG,658.,.98)                        2206400300008 
           (44-RU-103,39.5D,DG,498.,.885)                         2206400300009 
           (44-RU-105,4.43HR,DG,726.,.48)                         2206400300010 
           (52-TE-132,77.7HR,DG,228.,.94)                         2206400300011 
           (53-I-131,8.05D,DG,365.,.81)                           2206400300012 
           (53-I-133-G,20.8HR,DG,530.,.94)                        2206400300013 
           (53-I-135,6.7HR,DG,1263.,.34)                          2206400300014 
           (54-XE-135-G,9.2HR,DG,250.,.97)                        2206400300015 
           (55-CS-138-G,32.2MIN,DG,1436.,.73)                     2206400300016 
           (58-CE-141,32.5D,DG,145.,.50)                          2206400300017 
           (58-CE-143,33.HR,DG,293.,.426)                         2206400300018 
           (60-ND-147,11.1D,DG,91.,.287)                          2206400300019 
MONITOR    ((MONIT1)95-AM-241(N,F)42-MO-99,CUM,FY,,SPA) used for  2206400300020 
            normalization of the light-mass peak, i.E. A = 91     2206400300021 
            to 105.                                               2206400300022 
           ((MONIT2)95-AM-241(N,F)56-BA-139,CUM,FY,,SPA) used for 2206400300023 
            normalization of the heavy-mass peak, i.e. A = 131 to 2206400300024 
            147.                                                  2206400300025 
DECAY-MON  (42-MO-99,67.HR,DG,140.,.88)                           2206400300026 
           (43-TC-99-M,6.HR,DG,140.,.913)                         2206400300027 
           (56-BA-139,83.MIN,DG,166.,.224)                        2206400300028 
METHOD     (ACTIV) Determination of relative mass yields by direct2206400300029 
            gamma-ray spectrometry of several fission products    2206400300030 
            simultaneously.                                       2206400300031 
SAMPLE      Targets were prepared by drying pure (1/400 Pu-239)   2206400300032 
            Am-241 nitrate (about 900 ug Am-241 in 6 cm2 area)    2206400300033 
            on a 5.16 mg/cm2 Al foil, placed on a 0.3 mm thick    2206400300034 
            plastic frame, and with another Al foil used as a     2206400300035 
            catcher. Irradiation times were between 2 and 60 hr.  2206400300036 
ERR-ANALYS (DATA-ERR) The errors given are based on errors due to 2206400300037 
            gamma-counting and normalization.                     2206400300038 
STATUS     (TABLE) Table 2 of J.Inorg.Nucl.Chem.,33(1971)3239     2206400300039 
HISTORY    (19880808U) IF. Small corrections                      2206400300040 
           (19890130U) IF.                                        2206400300041 
           (19900829A) S.W. Flag and monitor clarified. Isomeric  2206400300042 
                     states added in decay-data.                  2206400300043 
           (20230209U) SD: BIB updated.                           2206400300044 
ENDBIB              42          0                                 2206400300045 
COMMON               4          3                                 2206400300046 
MONIT1     MONIT1-ERR MONIT2     MONIT2-ERR                       2206400300047 
PC/FIS     PC/FIS     PC/FIS     PC/FIS                           2206400300048 
     6.90        0.26       8.68      0.27                        2206400300049 
ENDCOMMON            3          0                                 2206400300050 
DATA                 5         15                                 2206400300051 
ELEMENT    ELEMENT    MASS       DATA       DATA-ERR              2206400300052 
NO-DIM     NO-DIM     NO-DIM     PC/FIS     PC/FIS                2206400300053 
        38.                   91.       1.48       0.43           2206400300054 
        38.                   92.       2.09       0.04           2206400300055 
        40.                   95.       4.04       0.21           2206400300056 
        40.        41.        97.       5.16       0.04           2206400300057 
        44.                  103.       7.65       0.23           2206400300058 
        44.                  105.       6.85       0.29           2206400300059 
        52.                  132.       4.70       0.02           2206400300060 
        53.                  131.       4.01       0.14           2206400300061 
        53.                  133.       7.46       0.30           2206400300062 
        53.                  135.       6.09       0.30           2206400300063 
        54.                  135.       6.80       0.28           2206400300064 
        55.                  138.       8.48       0.48           2206400300065 
        58.                  141.       6.29       0.31           2206400300066 
        58.                  143.       3.48       0.15           2206400300067 
        60.                  147.       1.81       0.20           2206400300068 
ENDDATA             17          0                                 2206400300069 
ENDSUBENT           68          0                                 2206400399999 
SUBENT        22064004   20230209   20231011                      2206400400001 
BIB                  5          8                                 2206400400002 
REACTION   (95-AM-241(N,F),,NU,,,DERIV)                           2206400400003 
ANALYSIS    nu-bar=242-<AL>-<AH>                                  2206400400004 
ERR-ANALYS (DATA-ERR) The errors given are based on errors due to 2206400400005 
            gamma-counting and normalization.                     2206400400006 
STATUS     (TABLE) Abstract of J.Inorg.Nucl.Chem.,33(1971)3239    2206400400007 
           (DEP,22064002)                                         2206400400008 
           (DEP,22064003)                                         2206400400009 
HISTORY    (20230209C) SD                                         2206400400010 
ENDBIB               8          0                                 2206400400011 
NOCOMMON             0          0                                 2206400400012 
DATA                 2          1                                 2206400400013 
DATA       DATA-ERR                                               2206400400014 
PRT/FIS    PRT/FIS                                                2206400400015 
      4.0          0.2                                            2206400400016 
ENDDATA              3          0                                 2206400400017 
ENDSUBENT           16          0                                 2206400499999 
ENDENTRY             4          0                                 2206499999999