ENTRY            21414   20090315                             22082141400000001 
SUBENT        21414001   20090315                             22082141400100001 
BIB                 14         19                                 2141400100002 
INSTITUTE  (2FR STR)                                              2141400100003 
REFERENCE  (J,JPR,12,6S,195101) Section de Strasbourg.            2141400100004 
AUTHOR     (P.Cuer,J-P.Longchamp,S.Gorodetzky)                    2141400100005 
TITLE      -Determination of the cross section for reactions of   2141400100006 
            thermal neutrons on nitrogen -.                       2141400100007 
FACILITY   (VDG  ) Van der graaff.                                2141400100008 
INC-SOURCE (D-BE ) 1 MeV deuterium beam on beryllium target,      2141400100009 
            with moderation in a cube of paraffin, 70 cm long.    2141400100010 
INC-SPECT  Maxwellian neutron spectrum at 293 deg K.              2141400100011 
SAMPLE     .Nitrogen in nuclear emulsion plates.                  2141400100012 
METHOD     (ASSOP) Associated proton detection.                   2141400100013 
DETECTOR   (TRD  ) Track detection in nuclear emulsion, ilford    2141400100014 
            E1, 50 micron.                                        2141400100015 
MONITOR    (5-B-0(N,A),,SIG,,MXW) Value taken as 703 B.           2141400100016 
STATUS     (NDD  ) Text, page 7S.                                 2141400100017 
HISTORY    (19800304T)                                            2141400100018 
           (19800318E)                                            2141400100019 
           (20090315U) Last checking has been done.               2141400100020 
ERR-ANALYS .One standard deviation, no details.                   2141400100021 
ENDBIB              19          0                                 2141400100022 
COMMON               1          3                                 2141400100023 
MONIT                                                             2141400100024 
B                                                                 2141400100025 
   7.03E+02                                                       2141400100026 
ENDCOMMON            3          0                                 2141400100027 
ENDSUBENT           26          0                                 2141400199999 
SUBENT        21414002   19800318                             00002141400200001 
BIB                  2          2                                 2141400200002 
REACTION   (7-N-14(N,P)6-C-14,,SIG,,MXW) CROSS SECTION.           2141400200003 
STATUS     (NDD  )                                                2141400200004 
ENDBIB               2          0                                 2141400200005 
NOCOMMON             0          0                                 2141400200006 
DATA                 3          1                                 2141400200007 
EN-DUMMY   DATA       DATA-ERR                                    2141400200008 
EV         B          B                                           2141400200009 
 2.5300E-02 1.7700E+00 9.0000E-02                                 2141400200010 
ENDDATA              3          0                                 2141400200011 
ENDSUBENT           10          0                                 2141400299999 
ENDENTRY             2          0                                 2141499999999