SUBENT        22089001   20201012                             22942208900100001 
BIB                 17        107                                 2208900100002 
TITLE       Activation cross section measurements for fusion      2208900100003 
            reactor structural materials at neutron energy from   2208900100004 
            13.3 to 15.0 MeV using FNS facility                   2208900100005 
AUTHOR     (Y.Ikeda,C.Konno,K.Oishi,T.Nakamura,H.Miyade, K.Kawade,2208900100006 
            H.Yamamoto, T.Katoh)                                  2208900100007 
REFERENCE  (R,JAERI-1312,1988)                                    2208900100008 
INSTITUTE  (2JPNJAE,2JPNNAG)                                      2208900100009 
REL-REF    (I,,H.Maekawa+,R,JAERI-M-83-219,1983) Associated       2208900100010 
            alpha-particles counting.                             2208900100011 
           (R,,C.M.Lederer+,B,LEDERER-7,,,1978) Reference for     2208900100012 
            half-life errors and gamma-ray emission probability   2208900100013 
           (M,,Nakagava+,R,JAERI-M-84-126,1984) Reference for     2208900100014 
            Monte Carlo code MORSE-DD used for neutron spectra    2208900100015 
            calculations.                                         2208900100016 
FACILITY   (CCW,2JPNJAE) JAERI FNS facility. Deuterons accelerated2208900100017 
            to 330 keV.  The beam current was 1.5 mA.             2208900100018 
INC-SOURCE (D-T) Water cooled Ti-T target. Neutron yield at       2208900100019 
                 target position was 2.0 x 10**11 n/sec.          2208900100020 
INC-SPECT  Source neutron spectra calculated by MORSE-DD at angles2208900100021 
            0, 45, 60, 80, 100, 120, 135, 165 deg are given in    2208900100022 
            Figures 8.1 - 8.8, 10 .                               2208900100023 
METHOD     (ACTIV)                                                2208900100024 
DETECTOR   (GELI) 5 GeLi detectors were used. Two of these served 2208900100025 
            as standard detectors, and the absolute efficiency of 2208900100026 
            these were determined with standard gamma-ray sources.2208900100027 
MONITOR    ((MONIT1)13-AL-27(N,A)11-NA-24,,SIG)                   2208900100028 
           ((MONIT2)41-NB-93(N,2N)41-NB-92-M,,SIG) 464 mb for     2208900100029 
            neutrons between 13.3 to 15.0 MeV. Determined relative2208900100030 
            to MONIT1. Used as neutron flux monitor.              2208900100031 
            Was used as a substandard for half-lives longer than  2208900100032 
            30 min while the reaction 13-Al-27(n,p)12-Mg-27 was   2208900100033 
            employed for the short-lived activities.              2208900100034 
           ((MONIT3)13-AL-27(N,P)12-MG-27,,SIG) As substandard.   2208900100035 
            Determined relative to MONIT1 with uncertainty 4.3%.  2208900100036 
            Numerical values of monitors used:                    2208900100037 
            EN-NRM (MeV)  MONIT1 (mb)   EN-NRM (MeV)  MONIT3 (mb) 2208900100038 
            14.96         113.42        14.93         62.29       2208900100039 
            14.92         113.93        14.76         60.92       2208900100040 
            14.84         114.97        14.66         66.05       2208900100041 
            14.71         116.65        14.43         64.18       2208900100042 
            14.53         118.97        14.04         71.08       2208900100043 
            14.32         121.28        13.52         77.84       2208900100044 
            14.10         123.63        13.33         83.29       2208900100045 
            13.95         125.02                                  2208900100046 
            13.81         125.93                                  2208900100047 
            13.68         126.77                                  2208900100048 
            13.55         127.62                                  2208900100049 
            13.33         128.60                                  2208900100050 
            In COMMON block the value of MONIT1 and MONIT3  at    2208900100051 
             EN-NRM1=13.33 MeV are given.                         2208900100052 
MONIT-REF  ((MONIT1),,3,ENDF/B-V,,1979) ENDF/B-V Dosimetry File.  2208900100053 
SAMPLE     Separated isotopes were used. If the sample was        2208900100054 
           powder, it (about 50.mg weight) was wrapped in a       2208900100055 
           cartridge paper with effective area of 1 cm2.          2208900100056 
           Samples were positioned at a distance of 10 cm from the2208900100057 
           target, in the angular interval 0 - 165 degrees, thus  2208900100058 
           covering the energy range 13.3 - 15.0 MeV.             2208900100059 
           Samples with short-lived activities were transported   2208900100060 
           along the pneumatic tube with a transfer time of       2208900100061 
           about 1 sec.                                           2208900100062 
           Two Nb foils of 10.mm x 10.mm x 0.1 mm for one         2208900100063 
           sample - for neutron flux monitoring.                  2208900100064 
CORRECTION  Corrections were applied for count loss due to        2208900100065 
            summation of cascade gammas, self-absorption in the   2208900100066 
            samples, fluctuation of the neutron flux during       2208900100067 
            irradiation, and for contribution of low energy       2208900100068 
            neutrons to the reaction rate.                        2208900100069 
ERR-ANALYS (ERR-T)    Different factors contributing to the       2208900100070 
                       total error                                2208900100071 
           (ERR-S,0.3,5.) Statistical error of gamma-ray counts   2208900100072 
                         between 0.3 - 5.%;                       2208900100073 
           (ERR-1,2.,3.) Error of detector efficiency             2208900100074 
                         between 2. - 3.%;                        2208900100075 
           (ERR-2,,0.1) Error of sample weight less than 0.1%     2208900100076 
           (ERR-3,,0.1) Error of irradiation, cooling and         2208900100077 
                   measuring time less than 0.1%                  2208900100078 
           (ERR-4,,0.5) Error of self-absorption less than 0.5%   2208900100079 
           (ERR-5,0.1,2.) Error of half-life; between 0.1 - 2.%;  2208900100080 
           (ERR-6,0.5,2.) Error of gamma-ray emission probability;2208900100081 
                         between 0.5 - 2.%;                       2208900100082 
           (ERR-7,,0.1) Error of correction for mean source       2208900100083 
                   position less than 0.1%                        2208900100084 
           (ERR-8,,0.1) Error of correction for fluctuation       2208900100085 
                        less than 0.1%                            2208900100086 
           (ERR-9,,0.1) Error of correction for cascade summing   2208900100087 
                        less than 0.1%                            2208900100088 
           (MONIT1-ERR) MONIT1 standard reaction cross section    2208900100089 
                        error                                     2208900100090 
           (MONIT2-ERR) Error of MONIT2.                          2208900100091 
           (MONIT3-ERR) Error of MONIT3.                          2208900100092 
STATUS     (TABLE) Data taken from Table 5 of JAERI-1312,1988     2208900100093 
HISTORY    (19881024C) N.O.                                       2208900100094 
           (19900828A) S.W. Flags added to numerous  subents.     2208900100095 
           (20040610A) DATE is corrected  -  SM                   2208900100096 
           (20070125A) SM: Data error in SAN064 corrected. Errors 2208900100097 
           structure given and DATA-ERR to ERR-T changed.         2208900100098 
           (20081020A) M.M. Misprint in Subent 096 was corrected. 2208900100099 
            Free text was corrected to be human-readable.         2208900100100 
            Monitors values were added. Misprints in decay data   2208900100101 
            were corrected in several Subents. Information in     2208900100102 
            STATUS lines was added.                               2208900100103 
           (20131228A) SD: REACTION code in Subent 106 was        2208900100104 
           corrected. ERR-ANALYS was corrected. Minor corrections.2208900100105 
           (20160721U) SD: STATUS 'COREL' added to Subent 098.    2208900100106 
           (20190208U) SD: STATUS 'COREL' added to several Subents2208900100107 
           (20201012A) SD: Corrections in all Subents.            2208900100108 
           The accuracy of data presentation  has been revised.   2208900100109 
ENDBIB             107          0                                 2208900100110 
COMMON               7          6                                 2208900100111 
EN-NRM1    MONIT1     MONIT1-ERR MONIT2     MONIT2-ERR MONIT3     2208900100112 
MONIT3-ERR                                                        2208900100113 
MEV        MB         PER-CENT   MB         PER-CENT   MB         2208900100114 
PER-CENT                                                          2208900100115 
      13.33     128.60        3.0       464.        4.2      83.292208900100116 
        4.3                                                       2208900100117 
ENDCOMMON            6          0                                 2208900100118 
ENDSUBENT          117          0                                 2208900199999 
SUBENT        22089099   20201012                             22942208909900001 
BIB                  4          4                                 2208909900002 
REACTION   (56-BA-135(N,P)55-CS-135-M,,SIG)                       2208909900003 
DECAY-DATA (55-CS-135-M,53.MIN,DG,781.,.997)                      2208909900004 
STATUS     (TABLE)  Table 5 from JAERI-1312  (Fig.11.98)          2208909900005 
HISTORY    (20201012U) SD: STATUS updated.                        2208909900006 
ENDBIB               4          0                                 2208909900007 
NOCOMMON             0          0                                 2208909900008 
DATA                 3          8                                 2208909900009 
EN         DATA       ERR-T                                       2208909900010 
MEV        MB         MB                                          2208909900011 
      14.95   3.60E-01    3.4E-02                                 2208909900012 
      14.68   3.07E-01    3.2E-02                                 2208909900013 
      14.44   2.93E-01    3.3E-02                                 2208909900014 
      14.23   2.62E-01    4.0E-02                                 2208909900015 
      13.99   2.97E-01    3.2E-02                                 2208909900016 
      13.76   2.53E-01    4.1E-02                                 2208909900017 
      13.57   2.16E-01    2.8E-02                                 2208909900018 
      13.34   2.40E-01    3.2E-02                                 2208909900019 
ENDDATA             10          0                                 2208909900020 
ENDSUBENT           19          0                                 2208909999999