SUBENT        22342001   20220215                             23092234200100001 
BIB                 15         60                                 2234200100002 
TITLE       Measurement of thermal neutron cross section and      2234200100003 
            resonance integral of the reaction 135-Cs(n,g)136-Cs  2234200100004 
AUTHOR     (T.Katoh,S.Nakamura,H.Harada,Y.Hatsukawa,N.Shinohara,  2234200100005 
           K.Hata,K.Kobayashi,S.Motoishi,M.Tanase)                2234200100006 
INSTITUTE  (2JPNPNC)  Katoh, nakamura, harada                     2234200100007 
           (2JPNJAE)  hatsukawa, shinohara, hata, kabayashi,      2234200100008 
                      motoishi, tanase                            2234200100009 
REFERENCE  (J,NST,34,431,1997)  Experimental details and          2234200100010 
                                      final results are   given   2234200100011 
           ((S,INDC(JPN)-179,222,1997)=                           2234200100012 
           (S,JAERI-C-97-005,222,1997))                           2234200100013 
            proceedings of symposium november 21-22 1996, JAERI,  2234200100014 
            Japan, published March 1997.  Final data are given.   2234200100015 
           (C,97TRIEST,2,1335,1997)                               2234200100016 
FACILITY   (REAC,2JPNJAE)  JRR-3 reactor                          2234200100017 
METHOD     (ACTIV)  Activation                                    2234200100018 
DETECTOR   (HPGE) Efficiency 90%, energy resolution 2.1 keV FWHM  2234200100019 
                  at 1333 keV gamma energy                        2234200100020 
MONITOR    ((MONIT1)27-CO-59(N,G)27-CO-60,,SIG)                   2234200100021 
           ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG)                 2234200100022 
                cobalt/aluminium and gold/aluminium alloys were   2234200100023 
                used for monitoring of neutron flux               2234200100024 
DECAY-MON  (27-CO-60-G,5.271YR,DG,1173.,0.9990,                   2234200100025 
                             DG,1332.,0.9998)                     2234200100026 
           (79-AU-198-G,2.696D,DG,412.,0.955)                     2234200100027 
SAMPLE      Cs-Cl solution poured in the quartz tube,             2234200100028 
            Cs-135/Cs-137 ratio was measured by the quadrupole    2234200100029 
            mass spectrometer                                     2234200100030 
            Cobalt monitor sample is 0.46% Co/Al alloy wire,      2234200100031 
            0.381 mm diam,99.9313% purity, weights 2.123 and      2234200100032 
            4.083 mg                                              2234200100033 
            Gold monitor sample is 0.112% Au/Al alloy wire,       2234200100034 
            0.510 mm diam,99.9845% purity, weights 0.518 and      2234200100035 
            0.506 mg                                              2234200100036 
INC-SPECT   Neutron irradiation of targets was performed at the   2234200100037 
            hydraulic tube facility of JRR-3 reactor. Samples     2234200100038 
            were irradiated with cadmium shield and without this  2234200100039 
             shield                                               2234200100040 
DECAY-DATA (55-CS-136-G,12.63D,DG,819.,0.9970,                    2234200100041 
                               DG,1048.,0.798,                    2234200100042 
                               DG,1235.,0.197)                    2234200100043 
           (55-CS-137,30.174YR,DG,662.,0.860)  tracer of Cs-135   2234200100044 
ERR-ANALYS (ERR-T) Total error consisting of statistical error    2234200100045 
                  (not given) and several systematic errors -     2234200100046 
                  ERR-1 to ERR-4                                  2234200100047 
           (ERR-1) error in the gamma-ray full energy peak        2234200100048 
                   efficiency                                     2234200100049 
           (ERR-2) error in the neutron flux measurement          2234200100050 
           (ERR-3) error in the emission probability per decay    2234200100051 
                   of each gamma-ray                              2234200100052 
           (ERR-4) error in the measurement of the isotopic ratio 2234200100053 
                   of 135-Cs/137-Cs by the quadrupole mass        2234200100054 
                   spectrometer                                   2234200100055 
STATUS     (TABLE) Tbl.9 from Nucl.Sci.Tech.,34(1997)431          2234200100056 
HISTORY    (19970715C)  + + Compiled by S. Maev  + +              2234200100057 
           (19980730U)  * * new reference added                   2234200100058 
           (20041204A)  .bib-info correcred, two subents added    2234200100059 
           (20220215A) SD:Updated to new date formats,lower case. 2234200100060 
           Year of the JAERI-C-97-005,222 ref.                    2234200100061 
           updated (1996 -> 1997).                                2234200100062 
ENDBIB              60          0                                 2234200100063 
COMMON               6          3                                 2234200100064 
MONIT1     MONIT2     ERR-1      ERR-2      ERR-3      ERR-4      2234200100065 
B          B          PER-CENT   PER-CENT   PER-CENT   PER-CENT   2234200100066 
   37.18     98.65       1.5        1.5        1.0        3.0     2234200100067 
ENDCOMMON            3          0                                 2234200100068 
ENDSUBENT           67          0                                 2234200199999 
SUBENT        22342002   20041204                             00002234200200001 
BIB                  1          1                                 2234200200002 
REACTION   (55-CS-135(N,G)55-CS-136,,SIG)                         2234200200003 
ENDBIB               1          0                                 2234200200004 
NOCOMMON             0          0                                 2234200200005 
DATA                 3          1                                 2234200200006 
EN         DATA       ERR-T                                       2234200200007 
EV         B          B                                           2234200200008 
   2.53E-02  8.300E+00  3.000E-01                                 2234200200009 
ENDDATA              3          0                                 2234200200010 
ENDSUBENT            9          0                                 2234200299999