ENTRY            41463   20150928                             41714146300000001 
SUBENT        41463001   20150928                             41714146300100001 
BIB                 16         31                                 4146300100002 
TITLE       Measurement of thermal neutron radiative capture      4146300100003 
            cross-sections of the 14-N And 19-F by in-beam        4146300100004 
            gamma-spectroscopy method with reactor neutrons       4146300100005 
AUTHOR     (A.I.Egorov,R.I.Krutova,Yu.E.Loginov,S.Eh.Malyutenkova)4146300100006 
INSTITUTE  (4RUSLIN)                                              4146300100007 
REFERENCE  (J,NIM/A,545,296,2005)                                 4146300100008 
FACILITY   (REAC,4RUSLIN) WWR-M Reactor                           4146300100009 
METHOD     (TOF) For neutron spectrum measuring.                  4146300100010 
           (GSPEC) Detection of prompt g-rays emitted following   4146300100011 
            neutron capture and of photons accompanying beta decay4146300100012 
            of residual nuclei.                                   4146300100013 
INC-SOURCE (REAC) External thermal neutron beam of WWR-M reactor. 4146300100014 
INC-SPECT   Narrow neutron spectrum,maximum at 0.028+-0.002 eV,   4146300100015 
            FWHM about 0.03 eV,most probable neutron velocity     4146300100016 
            2200m/s. Neutron flux at sample site 2.E+7 n/cm2/s.   4146300100017 
SAMPLE      Homogeneous mixture of chemical compounds             4146300100018 
            Pb(NO3), CaF2, LiF and Teflon with Al2O3.             4146300100019 
DETECTOR   (HPGE) Efficiency error <= 0.4% up to E-gamma 2 MeV.   4146300100020 
MONITOR    ((MONIT)13-AL-27(N,G)13-AL-28,,SIG)                    4146300100021 
MONIT-REF  (,S.F.Mughabghab+,B,NEUT.CS 1A,,1981)                  4146300100022 
DECAY-MON  (13-AL-28,2.24MIN,DG,1779.,1.)                         4146300100023 
ANALYSIS          Comparison of areas of g-lines in isotope under 4146300100024 
            investigation and in isotope used as standard.        4146300100025 
ERR-ANALYS (ERR-T) Total error (1.5-2.%)                          4146300100026 
           (ERR-1) Error of cross-section standards               4146300100027 
           (ERR-2) Error of gamma-efficiency of spectrometer      4146300100028 
           (ERR-3) Error of number of atoms determination         4146300100029 
HISTORY    (20060208C)  Compiled at CJD (M.M.)                    4146300100030 
           (20150928A) M.M. AUTHOR and TITLE were corrected.      4146300100031 
            NO-DIM -> PC/REAC for ASSUM (-ERR) values; REL deleted4146300100032 
            from ASSUMED reactions.                               4146300100033 
ENDBIB              31          0                                 4146300100034 
COMMON               8          6                                 4146300100035 
EN         EN-RSL-FW  ERR-1      ERR-2      ERR-3      MONIT      4146300100036 
MONIT-ERR  EN-ERR                                                 4146300100037 
EV         EV         PER-CENT   PER-CENT   PER-CENT   B          4146300100038 
B          EV                                                     4146300100039 
0.028      0.03       1.         0.5        0.1        0.231      4146300100040 
0.003       0.002                                                 4146300100041 
ENDCOMMON            6          0                                 4146300100042 
ENDSUBENT           41          0                                 4146300199999 
SUBENT        41463002   20150928                             41714146300200001 
BIB                  3          7                                 4146300200002 
REACTION   (7-N-14(N,G)7-N-15,,SIG) Weighted average of 8 runs of 4146300200003 
             measurements with various targets.                   4146300200004 
ASSUMED    (ASSUM1,7-N-14(N,G)7-N-15,,SPC)     Intensity of       4146300200005 
            1678. keV gamma-transition                            4146300200006 
           (ASSUM2,7-N-14(N,G)7-N-15,,SPC)      Intensity of      4146300200007 
            1885. keV gamma-transition                            4146300200008 
STATUS     (TABLE) From Table 1.                                  4146300200009 
ENDBIB               7          0                                 4146300200010 
COMMON               4          3                                 4146300200011 
ASSUM1     ASSUM1-ERR ASSUM2     ASSUM2-ERR                       4146300200012 
PC/REAC    PC/REAC    PC/REAC    PC/REAC                          4146300200013 
 7.96        0.09       18.73     0.16                            4146300200014 
ENDCOMMON            3          0                                 4146300200015 
DATA                 2          1                                 4146300200016 
DATA       ERR-T                                                  4146300200017 
MB         MB                                                     4146300200018 
     79.5    1.3                                                  4146300200019 
ENDDATA              3          0                                 4146300200020 
ENDSUBENT           19          0                                 4146300299999 
SUBENT        41463003   20150928                             41714146300300001 
BIB                  3          4                                 4146300300002 
REACTION   (9-F-19(N,G)9-F-20,,SIG) Weighted average of 13 runs of4146300300003 
             measurements with various targets.                   4146300300004 
DECAY-DATA (9-F-20,11.0SEC,DG,1633.,1.00)                         4146300300005 
STATUS     (TABLE) From Table 1.                                  4146300300006 
ENDBIB               4          0                                 4146300300007 
NOCOMMON             0          0                                 4146300300008 
DATA                 2          1                                 4146300300009 
DATA       ERR-T                                                  4146300300010 
MB         MB                                                     4146300300011 
     9.50    0.15                                                 4146300300012 
ENDDATA              3          0                                 4146300300013 
ENDSUBENT           12          0                                 4146300399999 
ENDENTRY             3          0                                 4146399999999