ENTRY            30651   20090830                             31403065100000001 
SUBENT        30651001   20090830                             31403065100100001 
BIB                 13         35                                 3065100100002 
INSTITUTE  (3AULCBR)                                              3065100100003 
REFERENCE  (J,NP/A,397,21,198303)                                 3065100100004 
AUTHOR     (C.M.Bartle,D.W.Gebbie,C.L.Hollas)                     3065100100005 
TITLE      Total cross sections for the Li-6(n,t)He-4 reaction    3065100100006 
           between 12 and 18 MeV                                  3065100100007 
EXP-YEAR   (1982)                                                 3065100100008 
FACILITY   (CYGFF,3AULCBR) Cyclograaff of the Australian National 3065100100009 
           University                                             3065100100010 
INC-SOURCE (D-D)                                                  3065100100011 
SAMPLE     6-Li-I(Eu) scintillator which serves simultaneously    3065100100012 
           both as the target and as the detector                 3065100100013 
METHOD     (ASSOP) Neutrons from the H-2(d,n)He-3 reaction are    3065100100014 
           electronically collimated through a 6-Li-I(Eu)         3065100100015 
           scintillator by counting the associated He-3 ions      3065100100016 
DETECTOR   (SCIN) 6-Li-I(Eu) scintillator                         3065100100017 
MONITOR    The neutron flux was determined by counting the number 3065100100018 
           of associated He-3 ions emmitted by the H-2(d,n)He-3   3065100100019 
           reaction                                               3065100100020 
HISTORY    (19830408C) DG.-                                       3065100100021 
           (20090725A) SD:Updated to new date formats,lower case. 3065100100022 
              Description of uncertainties and COMMON section     3065100100023 
              were added                                          3065100100024 
ERR-ANALYS (ERR-T) Following errors are combined in quadrature:   3065100100025 
           (ERR-1) The error in estimating the peak area - 5%     3065100100026 
           (ERR-S) The statistical error in the number of         3065100100027 
                   Li-6(n,a)H-3 events 2%                         3065100100028 
           (ERR-2) The error in estimating the attenuation of     3065100100029 
           the neutron beam - 20%                                 3065100100030 
           (ERR-3) Uncertainty in the integrated number of        3065100100031 
                   He-3 events - 2%                               3065100100032 
           (ERR-4) The error in counting the number of He-3       3065100100033 
                    events - 0.5%                                 3065100100034 
           (ERR-5) The scintillator thickness quoted by the       3065100100035 
                    manufacturer - 0.5%                           3065100100036 
           (ERR-6) Uncertainty in the multiple scattering - 1%    3065100100037 
ENDBIB              35          0                                 3065100100038 
COMMON               7          6                                 3065100100039 
ERR-1      ERR-2      ERR-3      ERR-4      ERR-5      ERR-6      3065100100040 
ERR-S                                                             3065100100041 
PER-CENT   PER-CENT   PER-CENT   PER-CENT   PER-CENT   PER-CENT   3065100100042 
PER-CENT                                                          3065100100043 
  5.0         20.        2.         0.5       0.5         1.      3065100100044 
  2.                                                              3065100100045 
ENDCOMMON            6          0                                 3065100100046 
ENDSUBENT           45          0                                 3065100199999 
SUBENT        30651002   20090830                             31403065100200001 
BIB                  3          9                                 3065100200002 
REACTION   (3-LI-6(N,T)2-HE-4,,SIG)                               3065100200003 
FLAG       (1.) First measurement                                 3065100200004 
           (2.) Second measurement for the same incident energy   3065100200005 
           (3.) Third measurement for the same incident energy    3065100200006 
           (4.) Fourth measurement for the same incident energy   3065100200007 
           (5.) Average of different measurements for the same    3065100200008 
                incident energy.                                  3065100200009 
STATUS     (TABLE) Data taken from Table 1                        3065100200010 
                             of Nucl.Phys.A397(1983)21.           3065100200011 
ENDBIB               9          0                                 3065100200012 
NOCOMMON             0          0                                 3065100200013 
DATA                 5         15                                 3065100200014 
EN         EN-RSL-FW  DATA       ERR-T      FLAG                  3065100200015 
MEV        KEV        MB         MB         NO-DIM                3065100200016 
 1.2000E+01 6.0000E+02 3.1700E+01 1.2000E+00 1.                   3065100200017 
 1.2000E+01 6.0000E+02 3.2600E+01 1.5000E+00 2.                   3065100200018 
 1.2000E+01            3.2200E+01 1.0000E+00 5.                   3065100200019 
 1.3700E+01 8.0000E+02 2.8500E+01 1.6000E+00 1.                   3065100200020 
 1.3700E+01 8.0000E+02 2.8900E+01 1.0000E+00 2.                   3065100200021 
 1.3700E+01            2.8700E+01 9.0000E-01 5.                   3065100200022 
 1.6500E+01 8.0000E+02 2.1200E+01 1.0000E+00 1.                   3065100200023 
 1.6500E+01 8.0000E+02 2.1900E+01 1.6000E+00 2.                   3065100200024 
 1.6500E+01 8.0000E+02 2.1600E+01 1.2000E+00 3.                   3065100200025 
 1.6500E+01 8.0000E+02 2.2100E+01 1.3000E+00 4.                   3065100200026 
 1.6500E+01 8.0000E+02 2.1700E+01 6.0000E-01 5.                   3065100200027 
 1.8200E+01 8.0000E+02 1.9000E+01 1.5000E+00 1.                   3065100200028 
 1.8200E+01 8.0000E+02 1.9000E+01 1.1000E+00 2.                   3065100200029 
 1.8200E+01 8.0000E+02 1.9600E+01 1.1000E+00 3.                   3065100200030 
 1.8200E+01            1.9200E+01 7.0000E-01 5.                   3065100200031 
ENDDATA             17          0                                 3065100200032 
ENDSUBENT           31          0                                 3065100299999 
ENDENTRY             2          0                                 3065199999999