SUBENT        22837001   20130113                             22342283700100001 
BIB                 18        104                                 2283700100002 
TITLE       .Measurements of activation cross sections of (n,p)   2283700100003 
             and (n,alpha) reactions with d-D neutrons in         2283700100004 
             the energy range 2.1 - 3.1 MeV                       2283700100005 
AUTHOR     (T.Shimizu,H.Sakane,M.Shibata,K.Kawade, T.Nishitani)   2283700100006 
INSTITUTE  (2JPNNAG) Shimizu, Sakane, Shibata, Kawade,            2283700100007 
               Dept. of Energy Engineering and Science.           2283700100008 
           (2JPNJAE) Nishitani, Dept.of Fusion Engineering        2283700100009 
REFERENCE  (J,ANE,31,975,2004)  Main reference, data are given    2283700100010 
REL-REF    (R,,R.B.Firestone+,B,FIRESTONE,,1996)  Decay constants 2283700100011 
              from the book of R.B.Firestone and V.S.Shirley,1996,2283700100012 
              Table of Isotopes,8th Edition, John Wiley & Sons,NY 2283700100013 
METHOD     (ACTIV)                                                2283700100014 
           (STTA)   Stack-target irradiation                      2283700100015 
FACILITY   (FNS,2JPNJAE)                                          2283700100016 
DETECTOR   (HPGE)  High-purity well-type germanium detector.      2283700100017 
                  A 22% HPGe detector was also used as a standard 2283700100018 
                  detector, its efficiency curve has been deter-  2283700100019 
                  mined with sourced of 241Am, 133Ba, 60Co, 24Na  2283700100020 
                  and 152Eu standard gamma sources                2283700100021 
INC-SOURCE (D-D)  Ti-D target bombarded with d+ beam of 350 keV   2283700100022 
            d+ ion current is 1-2 milli-amperes (most probable    2283700100023 
            1.2 mA)                                               2283700100024 
INC-SPECT  .Angles of irradiation positions with respect to the   2283700100025 
            incident d+ beam were 0, 45, 70, 95, 120, 155 degrees 2283700100026 
            which covered neutron energies between 2.1 and        2283700100027 
            3.1 MeV. Ratio of the 64Zn(n,p) reaction sigma to     2283700100028 
            that of 115In(n,n') determines well the neutron mean  2283700100029 
            energy. The typical neutron fluence rate was 5.E+6    2283700100030 
            to 1.E+8 n/cm2/sec. Maximum energy spread EN-RSL was  2283700100031 
            300 keV.                                              2283700100032 
           .14-MeV neutrons are present due to the admixture of   2283700100033 
            tritium in Ti-D target, part of 14-MeV neutron was    2283700100034 
             1.E-3 to 1.E-4 relative to the D-D neutrons          2283700100035 
MONITOR    ((MONIT)49-IN-115(N,INL)49-IN-115-M,,SIG)              2283700100036 
MONIT-REF  (,K.Kobayashi+,R,JAERI-1344,2002)  JENDL               2283700100037 
                                    dosimetry file-99 (DF99)      2283700100038 
DECAY-MON  (49-IN-115-M,4.486HR,DG,336.240,0.459)                 2283700100039 
CORRECTION  Corrections were made                                 2283700100040 
           -for the fractional contribution of the low-energy     2283700100041 
            neutrons, near 1%                                     2283700100042 
           -for the fluctuations of neutron fluence rate during   2283700100043 
            irradiation - 3%                                      2283700100044 
           -for counting loss owing to the summing effect of the  2283700100045 
            true coincidence and random coincidence - 2%          2283700100046 
           -for deviation of detection efficiency owing to sample 2283700100047 
            thickness - 3%                                        2283700100048 
           -for self-absorption of Gamma-rays in sample -         2283700100049 
            negligible                                            2283700100050 
           -for the interfering reactions - negligible            2283700100051 
           -for D-T 14-MeV neutrons from tritium contamination in 2283700100052 
            the target. In some cases comparable with the         2283700100053 
            measured cross section                                2283700100054 
SAMPLE      Zinc and indium samples were used as standards.       2283700100055 
             115In sample is metallic of natural isotopic content 2283700100056 
            - 95.71% of 115In - weight 150 milligram, thickness   2283700100057 
            0.2 mm, chemical purity 99.9%,                        2283700100058 
            64Zn sample is metallic of natural isotopic content   2283700100059 
            - 48.6 % of 64Zn - weight 350 milligram, thickness    2283700100060 
            0.5 mm, chemical purity 99.99%                        2283700100061 
            Samples were separated isotopes or naturally abundant 2283700100062 
            materials. Metallic samples in the foil form were     2283700100063 
            10*10 mm squares 0.2 mm thick.                        2283700100064 
            Samples in powder form were wrapped with the thin car-2283700100065 
            tridge paper and they were typically 1-2 mm thick,    2283700100066 
            weight 50-90 mg                                       2283700100067 
            Details are given in the proper subents               2283700100068 
ERR-ANALYS (ERR-T)  Total error, quadratic sum of the experimental2283700100069 
              (systematic error ERR-SYS) and error of the nuclear 2283700100070 
              data ERR-1                                          2283700100071 
           .ERR-SYS - Total systematic error equal to the sum of  2283700100072 
                      all experimental errors                     2283700100073 
           (ERR-S,2.,40.)  Error of counting statistics           2283700100074 
           (ERR-1)  Error of the nuclear data including standard  2283700100075 
                    sigma 115In(n,n') error, Gamma-ray emission   2283700100076 
                    probability error and half-life error         2283700100077 
           (ERR-2,,0.6)  Error from the low-energy neutrons       2283700100078 
           (ERR-3,1.5,50.)  Error from 14-MeV neutrons            2283700100079 
           (ERR-5,,0.4) Error from fluctuations of neutron fluence2283700100080 
           (ERR-6,1.5,3.)  Error of detector efficiency for       2283700100081 
              gamma-ray energy between 80 and 300 keV is 3.%      2283700100082 
             Error of detector efficiency for gamma-ray energy    2283700100083 
             more than 300 keV is 1.5%                            2283700100084 
           (ERR-8,1.2,10.) Error of detector efficiency           2283700100085 
                           calibration                            2283700100086 
           (ERR-10,,0.6) Error of the true coincidence sum        2283700100087 
           (ERR-11) Error of the sample weight                    2283700100088 
           (ERR-12,,0.6) Error of sample thickness                2283700100089 
           (ERR-13,,0.2) Error of the self-absorpt. of gamma-rays 2283700100090 
           (ERR-15) Error of the Gamma-ray peak evaluation        2283700100091 
           (ERR-HL) Half-life error                               2283700100092 
           (ERR-EDD) Error of gamma energy                        2283700100093 
           (ERR-IDD) Error of gamma emission probability          2283700100094 
           (MONIT-ERR)  error of the standard cross section       2283700100095 
                        115In(n,n')115In-M                        2283700100096 
           (EN-ERR)   Center of energy distribution error arising 2283700100097 
             from the ambiguity of d+ beam position  in the       2283700100098 
             accelerating tube and inherent error of Zn/In method 2283700100099 
STATUS     (TABLE) .From table 5 of ANE,31,975                    2283700100100 
           (APRVD)   Shimizu, 2005-02-15                          2283700100101 
HISTORY    (20040729C)  JOS                                       2283700100102 
           (20050218U) SM. Approved by Shimizu, 2005-02-15        2283700100103 
           (20130113A) SD: DECAY-MON was corrected; MONITOR       2283700100104 
            reaction Zn-64(n,p)Cu-64 was deleted (not for         2283700100105 
            neutron flux determination).                          2283700100106 
ENDBIB             104          0                                 2283700100107 
COMMON               5          3                                 2283700100108 
EN-ERR     ERR-11     ERR-15     MONIT-ERR  EN-RSL                2283700100109 
KEV        PER-CENT   PER-CENT   PER-CENT   KEV                   2283700100110 
        50.        0.1        0.5         3.       300.           2283700100111 
ENDCOMMON            3          0                                 2283700100112 
ENDSUBENT          111          0                                 2283700199999 
SUBENT        22837013   20040729                             00002283701300001 
BIB                  3          5                                 2283701300002 
REACTION   (35-BR-79(N,P)34-SE-79-M,,SIG)                         2283701300003 
DECAY-DATA (34-SE-79-M,3.91MIN,DG,95.73,0.095)                    2283701300004 
SAMPLE     .Potassium bromide K-Br  powder, weight 82 mg, thicknes2283701300005 
            1.70 mm, chemical purity 99.9%, natural isotopic      2283701300006 
            abundance - Br-79 content 50.697                      2283701300007 
ENDBIB               5          0                                 2283701300008 
COMMON               9          6                                 2283701300009 
ERR-1      ERR-HL     ERR-EDD    ERR-IDD    ERR-HL    AERR-EDD   A2283701300010 
ERR-IDD   AERR-HL    BERR-IDD   B                                 2283701300011 
PER-CENT   MIN        KEV        NO-DIM     HR         KEV        2283701300012 
NO-DIM     HR         NO-DIM                                      2283701300013 
    4.5        0.05      0.03       0.003     0.004        0.012  2283701300014 
    0.001    0.002        0.014                                   2283701300015 
ENDCOMMON            6          0                                 2283701300016 
DATA                 4          1                                 2283701300017 
EN         DATA       ERR-T      MONIT     A                      2283701300018 
MEV        MB         MB         MB                               2283701300019 
       3.09    0.48       0.06     339.11                         2283701300020 
ENDDATA              3          0                                 2283701300021 
ENDSUBENT           20          0                                 2283701399999