ENTRY            21391   20070409                             21842139100000001 
SUBENT        21391001   20070409                             21842139100100001 
BIB                 14         17                                 2139100100002 
INSTITUTE  (2GERJUL)                                              2139100100003 
REFERENCE  (J,NUK,10,257,196711)                                  2139100100004 
AUTHOR     (K.H.Robrock,R.Hecker)                                 2139100100005 
TITLE      -The effective reaction cross section for be-9(N,2N)   2139100100006 
            from helium gas measurement in a beryllium probe -.   2139100100007 
FACILITY   (REAC ) Br 2 reactor, Mol, Belgium.                    2139100100008 
INC-SOURCE (REAC ) Reactor neutrons.                              2139100100009 
SAMPLE     .Berillium metal foil, 8 mm diameter, 10 mm long.      2139100100010 
METHOD     (CHSEP) Chemical seperation of helium gas.             2139100100011 
DETECTOR   .Helium gas pressure measurement.                      2139100100012 
PART-DET   (A)     Helium gas.                                    2139100100013 
STATUS     (NDD)   Text in nuk,10,257.                            2139100100014 
CORRECTION .Corrected for contributions from other reactions.     2139100100015 
ERR-ANALYS .One standard deviation given.                         2139100100016 
HISTORY    (19800222T)                                            2139100100017 
           (19800303E)                                            2139100100018 
           (20070314A) Date is corrected                          2139100100019 
ENDBIB              17          0                                 2139100100020 
NOCOMMON             0          0                                 2139100100021 
ENDSUBENT           20          0                                 2139100199999 
SUBENT        21391002   20070409                             21842139100200001 
BIB                  5          6                                 2139100200002 
REACTION   (4-BE-9(N,2N+A)2-HE-4,,SIG,,MXW,DERIV) Cross section.  2139100200003 
INC-SPECT  .Reactor spectrum low energy cut off.                  2139100200004 
ANALYSIS   .Derived from measurement in spectrum with a mean      2139100200005 
            energy of 1 MeV, multiplied by a calculated factor.   2139100200006 
STATUS     (NDD)                                                  2139100200007 
HISTORY    (20070314A)   Reaction code corrected                  2139100200008 
ENDBIB               6          0                                 2139100200009 
NOCOMMON             0          0                                 2139100200010 
DATA                 3          1                                 2139100200011 
EN-DUMMY   DATA       DATA-ERR                                    2139100200012 
EV         MB         MB                                          2139100200013 
   2.53E-02    9.6E+01    1.3E+01                                 2139100200014 
ENDDATA              3          0                                 2139100200015 
ENDSUBENT           14          0                                 2139100299999 
SUBENT        21391003   20070409                             21842139100300001 
BIB                  5          9                                 2139100300002 
REACTION   (4-BE-9(N,2N+A)2-HE-4,,SIG,,FIS) Fission spectrum      2139100300003 
            average cross section.                                2139100300004 
INC-SPECT  Fission neutrons, mean energy 2.7 MeV                  2139100300005 
ANALYSIS   .Derived from measurement in spectrum with 1 MeV       2139100300006 
            mean neutron energy, multiplied by a calculated       2139100300007 
            factor of 2.7624 .                                    2139100300008 
STATUS     (NDD)   Text page 258.                                 2139100300009 
HISTORY    (19800218T)                                            2139100300010 
           (20070314A)   Reaction code corrected                  2139100300011 
ENDBIB               9          0                                 2139100300012 
NOCOMMON             0          0                                 2139100300013 
DATA                 3          1                                 2139100300014 
EN-DUMMY   DATA-MIN   DATA-MAX                                    2139100300015 
MEV        MB         MB                                          2139100300016 
        2.7    4.2E+02    5.3E+02                                 2139100300017 
ENDDATA              3          0                                 2139100300018 
ENDSUBENT           17          0                                 2139100399999 
ENDENTRY             3          0                                 2139199999999