SUBENT        14322001   20120413                             13821432200100001 
BIB                 17         35                                 1432200100002 
TITLE      Quantitative Tests of s-PROCESS in Stellar             1432200100003 
           Nucleosynthesis for Solar System Material              1432200100004 
AUTHOR     (R.L.Macklin,J.H.Gibbons)                              1432200100005 
INSTITUTE  (1USAORL)                                              1432200100006 
REFERENCE  (J,AJ,149,577,1967)                                    1432200100007 
REL-REF    (M,11380001,R.L.Macklin+,J,NP,43,353,1963)             1432200100008 
           (I,11679001,R.L.Macklin+,J,PR,159,1007,1967)           1432200100009 
FACILITY   (VDG,1USAORL)                                          1432200100010 
SAMPLE     Isotopic samples were obtained on loan from the AEC    1432200100011 
           Division of Research Cross Section Pool.               1432200100012 
INC-SOURCE (P-LI7) Pulsed neutrons are produced by ~1 nsec        1432200100013 
           bursts of protons which bombard a 7Li target.          1432200100014 
INC-SPECT  The neutron energy spread(FWHM), governed by the 7Li   1432200100015 
           target thickness and proton energy spread,             1432200100016 
           was about 15 keV.                                      1432200100017 
DETECTOR   (COIN,SCIN,NAICR) Two non-hydrogenous liquid           1432200100018 
           scintillators (Nuclear Enterprises Ltd. : NE-226)      1432200100019 
           gamma detectors gated on 10B-NaI neutron monitor.      1432200100020 
PART-DET   (G,N)                                                  1432200100021 
METHOD     (COINC,GSPEC,TOF,PHD) The protons,                     1432200100022 
           and thus neutrons, are produced in short (~1 nsec)     1432200100023 
           bursts spaced a microsecond apart, thus allowing       1432200100024 
           discrimination of events in time and a consequent      1432200100025 
           reduction in background.                               1432200100026 
ANALYSIS   Data were normalized to the previously determined      1432200100027 
           capture cross section on tantalum. The microscopic     1432200100028 
           capture cross sections were converted to effective     1432200100029 
           capture cross sections in a Maxwellian neutron flux    1432200100030 
           of temperature T.                                      1432200100031 
ERR-ANALYS (DATA-ERR) No details are given.                       1432200100032 
CORRECTION The raw data were corrected for sample scattering      1432200100033 
           effects (in the keV energy range G(n) >> G(gamma)) and 1432200100034 
           for resonance self shielding.                          1432200100035 
MONITOR    (73-TA-181(N,G)73-TA-182,,SIG,,MXW)                    1432200100036 
HISTORY    (20120413C) BP                                         1432200100037 
ENDBIB              35          0                                 1432200100038 
NOCOMMON             0          0                                 1432200100039 
ENDSUBENT           38          0                                 1432200199999 
SUBENT        14322019   20120413                             13821432201900001 
BIB                  2          2                                 1432201900002 
REACTION   (40-ZR-92(N,G)40-ZR-93,,SIG,,MXW)                      1432201900003 
STATUS     (TABLE) Table 4, page 585.                             1432201900004 
ENDBIB               2          0                                 1432201900005 
NOCOMMON             0          0                                 1432201900006 
DATA                 3          1                                 1432201900007 
KT         DATA       DATA-ERR                                    1432201900008 
KEV        MB         MB                                          1432201900009 
        30.        34.         6.                                 1432201900010 
ENDDATA              3          0                                 1432201900011 
ENDSUBENT           10          0                                 1432201999999