ENTRY            30339   20090115                             31343033900000001 
SUBENT        30339001   20090115                             31343033900100001 
BIB                 17         42                                 3033900100002 
INSTITUTE  (3ARGCNE)                                              3033900100003 
REFERENCE  (J,JIN,38,1386,197607)                                 3033900100004 
AUTHOR     (J.J.Gil Gerbino, I.M.Cohen, R.O.Korob, G.B.Baro)      3033900100005 
TITLE      Fission neutron averaged cross-section of              3033900100006 
           Tl-203(n,2n)Tl-202 reaction                            3033900100007 
EXP-YEAR   (1975)                                                 3033900100008 
FACILITY   (REAC,3ARGCNE) RA-3 light water reactor                3033900100009 
INC-SOURCE (REAC) Reactor. The fast flux in the irradiation box   3033900100010 
           was about 10**13 neutrons/(cm2*sec).                   3033900100011 
INC-SPECT  Using four standard reactions of different threshold   3033900100012 
           energies no departures from a fission spectrum were    3033900100013 
           found. No additional information given.                3033900100014 
           Compiler's comment:  Note that, although the threshold 3033900100015 
           energy of the reaction concerned is above 7 MeV, a     3033900100016 
           'dummy-energy' for the fission neutron spectrum of     3033900100017 
           2 MeV had to be entered.                               3033900100018 
METHOD     (ACTIV) Activation method                              3033900100019 
DETECTOR   (GELI) Germanium-lithium detector. The efficiency      3033900100020 
           curve was obtained using standardized sources followed 3033900100021 
           by least square fitting, the absolute efficiency by    3033900100022 
           comparison with a Cs-137 source.                       3033900100023 
MONITOR    Four different standard reactions were used. For the   3033900100024 
           results obtained with the different standards see      3033900100025 
           subentries 002-005.                                    3033900100026 
           The values of the standard cross-sections were taken   3033900100027 
           from A.Calamand, Handbook on Nuclear Activation Cross- 3033900100028 
           sections, pg.273, Technical report series no.156,      3033900100029 
           IAEA, Vienna (1974).                                   3033900100030 
PART-DET   (DG) Decay gammas                                      3033900100031 
DECAY-DATA (81-TL-202-G,12.23D)                                   3033900100032 
COMMENT    Authors calculated a mean value of the measurements    3033900100033 
           with 4 different standards = 4.0 +- 0.32 mb.           3033900100034 
STATUS     (TABLE) Data taken from J.Inorg.Nucl.Chem.38(1976)1386.3033900100035 
HISTORY    (19760831C) OS.                                        3033900100036 
           (20090125A) BIB section updated                        3033900100037 
ERR-ANALYS No errors of the individual measurements are given.    3033900100038 
           The error of the mean value includes:                  3033900100039 
           (ERR-1) errors of efficiency determination and due to  3033900100040 
            the dispersion of the obtained cross-section values   3033900100041 
             (1.8%)                                               3033900100042 
           (ERR-2) error of standard cross sections (6.2%).       3033900100043 
           No information on statistical errors given.            3033900100044 
ENDBIB              42          0                                 3033900100045 
COMMON               3          3                                 3033900100046 
EN-DUMMY   ERR-1      ERR-2                                       3033900100047 
MEV        PER-CENT   PER-CENT                                    3033900100048 
 2.0000E+00  1.8        6.2                                       3033900100049 
ENDCOMMON            3          0                                 3033900100050 
ENDSUBENT           49          0                                 3033900199999 
SUBENT        30339002   20090115                             31343033900200001 
BIB                  3          4                                 3033900200002 
REACTION   (81-TL-203(N,2N)81-TL-202,,SIG,,FIS)                   3033900200003 
ANALYSIS   Average of two measurements (3.98 and 3.95 mb,         3033900200004 
            respectively).                                        3033900200005 
MONITOR    (26-FE-54(N,P)25-MN-54,,SIG,,FIS)                      3033900200006 
ENDBIB               4          0                                 3033900200007 
NOCOMMON             0          0                                 3033900200008 
DATA                 3          1                                 3033900200009 
DATA       MONIT      MONIT-ERR                                   3033900200010 
MB         MB         MB                                          3033900200011 
 3.9650E+00 8.2500E+01 5.0000E+00                                 3033900200012 
ENDDATA              3          0                                 3033900200013 
ENDSUBENT           12          0                                 3033900299999 
SUBENT        30339003   20090115                             31343033900300001 
BIB                  3          4                                 3033900300002 
REACTION   (81-TL-203(N,2N)81-TL-202,,SIG,,FIS)                   3033900300003 
ANALYSIS   Average of two measurements (4.00 and 4.01 mb,         3033900300004 
            respectively).                                        3033900300005 
MONITOR    (28-NI-58(N,P)27-CO-58,,SIG,,FIS)                      3033900300006 
ENDBIB               4          0                                 3033900300007 
NOCOMMON             0          0                                 3033900300008 
DATA                 3          1                                 3033900300009 
DATA       MONIT      MONIT-ERR                                   3033900300010 
MB         MB         MB                                          3033900300011 
 4.0050E+00 1.1300E+02 7.0000E+00                                 3033900300012 
ENDDATA              3          0                                 3033900300013 
ENDSUBENT           12          0                                 3033900399999 
SUBENT        30339004   20090115                             31343033900400001 
BIB                  2          2                                 3033900400002 
REACTION   (81-TL-203(N,2N)81-TL-202,,SIG,,FIS)                   3033900400003 
MONITOR    (12-MG-24(N,P)11-NA-24,,SIG,,FIS)                      3033900400004 
ENDBIB               2          0                                 3033900400005 
NOCOMMON             0          0                                 3033900400006 
DATA                 3          1                                 3033900400007 
DATA       MONIT      MONIT-ERR                                   3033900400008 
MB         MB         MB                                          3033900400009 
 4.0600E+00 1.5300E+00 9.0000E-02                                 3033900400010 
ENDDATA              3          0                                 3033900400011 
ENDSUBENT           10          0                                 3033900499999 
SUBENT        30339005   20090115                             31343033900500001 
BIB                  2          2                                 3033900500002 
REACTION   (81-TL-203(N,2N)81-TL-202,,SIG,,FIS)                   3033900500003 
MONITOR    (13-AL-27(N,A)11-NA-24,,SIG,,FIS)                      3033900500004 
ENDBIB               2          0                                 3033900500005 
NOCOMMON             0          0                                 3033900500006 
DATA                 3          1                                 3033900500007 
DATA       MONIT      MONIT-ERR                                   3033900500008 
MB         MB         MB                                          3033900500009 
 4.0100E+00 7.2500E-01 4.5000E-02                                 3033900500010 
ENDDATA              3          0                                 3033900500011 
ENDSUBENT           10          0                                 3033900599999 
ENDENTRY             5          0                                 3033999999999