ENTRY            12904   19850212                             00001290400000001 
SUBENT        12904001   19850212                             00001290400100001 
BIB                 17         42                                 1290400100002 
INSTITUTE  (1USAANL)                                              1290400100003 
REFERENCE  (J,ANE,11,623,8412)                                    1290400100004 
           (R,ANL-NDM-86,8407)                                    1290400100005 
AUTHOR     (I.KANNO,J.W.MEADOWS,D.L.SMITH)                        1290400100006 
TITLE      MEASURED ACTIVATION CROSS SECTIONS BELOW 10 MEV FOR THE1290400100007 
            51-V(N,P)51-TI AND 51-V(N,ALPHA)48-SC REACTIONS.      1290400100008 
FACILITY   ANL FAST NEUTRON GENERATOR FACILITY                    1290400100009 
INC-SPECT  SEE ANL/NDM-4 FOR METHOD OF DERIVING NEUTRON RESOLUTION1290400100010 
METHOD     (ACTIV)                                                1290400100011 
DETECTOR   (GELI)                                                 1290400100012 
DECAY-DATA (21-SC-48,43.67HR,DG,984.,1.,DG,1037.,0.975,           1290400100013 
           DG,1312.,1.)                                           1290400100014 
SAMPLE     METALLIC SAMPLE 99.8+-0.2 PERCENT V BY WEIGHT.         1290400100015 
           ISOTOPIC ABUNDANCE OF 51-V ASSUMED TO BE 99.750 PERCENT1290400100016 
ANALYSIS   SEE ANL-NDM-9(74) AND ANL-7989(73) FOR DETAILS.        1290400100017 
ERR-ANALYS THE ENERGY UNCERTAINTY IS ABOUT 20 PERCENT OF          1290400100018 
            RESOLUTION FOR THE NEUTRON ENERGY DISTRIBUTIONS,      1290400100019 
            31-47 KEV.                                            1290400100020 
           (ERR-T) TOTAL UNCERTAINTY                              1290400100021 
                   DETAILED ERROR CORRELATION MATRIX IS GIVEN     1290400100022 
                     IN THE ANL REPORT                            1290400100023 
          1(ERR-S) RANDOM UNCERTAINTY                             1290400100024 
                     SEVEN SOURCES OF RANDOM ERRORS               1290400100025 
           (ERR-1) SYSTEMATIC UNCERTAINTY                         1290400100026 
                     TWELVE SOURCES OF SYSTEMATIC ERRORS          1290400100027 
CORRECTION CORRECTIONS WERE MADE FOR-                             1290400100028 
             . DETECTOR EFFICIENCY                                1290400100029 
             . BACKGROUND EFFECTS                                 1290400100030 
             . FISSION EVENTS OF LOW-ENERGY                       1290400100031 
             . FISSION PRODUCED BY BACKGROUND NEUTRONS            1290400100032 
             . NEUTRON MULTIPLE SCATTERING                        1290400100033 
             . GEOMETRY FACTORS                                   1290400100034 
             . NEUTRON SOURCE PROPERTIES                          1290400100035 
             . NEUTRON ABSORPTION                                 1290400100036 
             . SECONDARY NEUTRONS FROM D(D,N) SOURCES             1290400100037 
ADD-RES    CALCULATED THE FOLLOWING FROM MEASURED DATA -          1290400100038 
            U-235 FISSION SPECTRUM AVG. CROSS SECTION = 0.02377 MB1290400100039 
            CF-252 FISSION SPECTRUM AVG. CROSS SECTION = .03887 MB1290400100040 
COMMENT    SEE DATA SET 12898 FOR 51-V(N,P).                      1290400100041 
STATUS     (APRVD) D.L.SMITH, 84/11/11.                           1290400100042 
HISTORY    (841018C)                                              1290400100043 
           (850212A) REFERENCE UPDATE.                            1290400100044 
ENDBIB              42          0                                 1290400100045 
NOCOMMON             0          0                                 1290400100046 
ENDSUBENT           45          0                                 1290400199999 
SUBENT        12904002   19840831                             00001290400200001 
BIB                  3          5                                 1290400200002 
REACTION  1((23-V-51(N,A)21-SC-48,,SIG)/(92-U-238(N,F),,SIG))     1290400200003 
          2(23-V-51(N,A)21-SC-48,,SIG)                            1290400200004 
INC-SOURCE (D-D)                                                  1290400200005 
MONITOR   2(92-U-238(N,F),,SIG) ENDF/B-V FISSION CROSS SECTION    1290400200006 
            USED TO OBTAIN THE ABSOLUTE CROSS SECTION.            1290400200007 
ENDBIB               5          0                                 1290400200008 
NOCOMMON             0          0                                 1290400200009 
DATA                10         20                                 1290400200010 
EN         EN-RSL-FW  DATA      1ERR-S     1ERR-1     1ERR-T     11290400200011 
MONIT     2MONIT-ERR 2DATA      2ERR-T     2                      1290400200012 
MEV        MEV        NO-DIM     PER-CENT   PER-CENT   PER-CENT   1290400200013 
MB         PER-CENT   MB         PER-CENT                         1290400200014 
 5.515      0.191      2.705  -06 22.7        9.2       24.5      1290400200015 
 549.4      2.6        0.001486   24.6                            1290400200016 
 5.802      0.176      4.923  -06  5.9       11.6       13.0      1290400200017 
 586.8      2.6        0.002889   13.3                            1290400200018 
 6.073      0.166      1.203  -05  2.7       12.8       13.1      1290400200019 
 639.5      3.9        0.007693   13.7                            1290400200020 
 6.338      0.161      2.711  -05 12.8       10.3       16.4      1290400200021 
 746.6      3.9        0.02024    16.9                            1290400200022 
 6.338      0.158      2.826  -05  2.6       10.1       10.4      1290400200023 
 746.6      3.9        0.02110    11.1                            1290400200024 
 6.598      0.153      4.646  -05  7.3        8.6       11.3      1290400200025 
 839.2      3.9        0.03899    11.9                            1290400200026 
 6.598      0.154      5.230  -05  2.5        8.7        9.1      1290400200027 
 839.2      3.9        0.04389     9.9                            1290400200028 
 6.856      0.161      9.074  -05  2.5        9.1        9.4      1290400200029 
 901.4      3.9        0.08179    10.2                            1290400200030 
 7.110      0.170      1.677  -04  6.0        9.6       11.3      1290400200031 
 936.2      3.9        0.1570     12.0                            1290400200032 
 7.110      0.169      1.690  -04  2.4        9.5        9.8      1290400200033 
 936.2      3.9        0.1582     10.5                            1290400200034 
 7.363      0.173      2.809  -04  4.1        8.6        9.5      1290400200035 
 969.2      3.9        0.2722     10.3                            1290400200036 
 7.583      0.175      4.597  -04  3.5        8.4        9.1      1290400200037 
 987.7      3.9        0.4540      9.9                            1290400200038 
 7.862      0.184      7.849  -04  2.3        6.0        6.4      1290400200039 
 989.9      3.9        0.7770      7.5                            1290400200040 
 8.108      0.193      1.041  -03  2.7        7.0        7.5      1290400200041 
 991.8      2.9        1.032       8.0                            1290400200042 
 8.354      0.197      1.471  -03  2.6        6.4        6.9      1290400200043 
 993.6      2.9        1.462       7.5                            1290400200044 
 8.598      0.206      2.031  -03  2.8        5.0        5.7      1290400200045 
 995.4      2.9        2.022       6.4                            1290400200046 
 8.843      0.215      2.328  -03  2.7        5.7        6.3      1290400200047 
 997.2      2.9        2.321       6.9                            1290400200048 
 9.085      0.216      3.046  -03  3.4        4.9        6.0      1290400200049 
 997.0      2.9        3.037       6.6                            1290400200050 
 9.326      0.224      3.341  -03  3.5        4.6        5.8      1290400200051 
 993.1      2.9        3.318       6.5                            1290400200052 
 9.567      0.233      4.004  -03  3.5        4.5        5.7      1290400200053 
 989.1      2.9        3.960       6.4                            1290400200054 
ENDDATA             44          0                                 1290400200055 
ENDSUBENT           54          0                                 1290400299999 
ENDENTRY             2          0                                 1290499999999