SUBENT        31453001     951111   20050616   20050926       0000
BIB                 13         30
TITLE      Measurement of neutron radiative capture cross
           section for the Fe-56(n,g)Fe-57 reaction from 9.0 to
           20.0 MeV.
AUTHOR     (HOU LONG,HUANG ZHENGDE,ZHU LIHUA,DING DAZHAO)
INSTITUTE  (3CPRAEP)
REFERENCE  (J,CNP,16,(4),344,94)
FACILITY   (VDGT) HI-13 Tandem accelerator, CIAE.
INC-SOURCE (D-D) Neutron production target consisted of a gas
           cell. The deuteron beam was chopped and bunched to
           produce 1 ns bursts at a frequency of 4 MHz.
SAMPLE     Two cylindrical samples of natural iron, with dimen-
           sions 3.0*2.8 cm and 2.0*2.8 cm. The first one was
           used at 90 degree, the other at 55 and 125 degree
           with respect tot the deuteron beam.
DETECTOR   (NAICR) Two plastic-NaI anticoincidence shielded
           spectrometers.
METHOD     (TOF) The time-of-flight method was used to discrimi-
           nate the neutrons and gamma-rays and to eliminate
           events not associated with prompt gamma-rays. The
           background spectrum was obtained from the NaI spec-
           trum gated by a window equivalent in width to the
           gamma-ray peak window, at constant background in the
           TOF spectrum.
CORRECTION The gamma spectrum was corrected for background.
           also corrections were made, by a Monte Carlo code,
           for finite geometry, gamma-ray attenuation, neutron
           attenuation and multiple scattering in the sample.
ERR-ANALYS No error analysis given.
HISTORY    (951114C) HW.-
STATUS     Data are taken from author ( private communication).
ENDBIB              30
NOCOMMON             0          0
ENDSUBENT           33
SUBENT        31453003     951111   20050616   20050926       0000
BIB                  1          1
REACTION   (26-FE-56(N,G)26-FE-57,,DA)
ENDBIB               1
NOCOMMON             0          0
DATA                 4         10
ANG        EN         DATA       DATA-ERR
ADEG       MEV        MU-B/SR    MU-B/SR
55.        9.0               717.       107.
55.        10.0              719.       108.
55.        12.5              654.        98.
55.        15.0              573.        86.
55.        20.0              264.        40.
125.       9.0               594.        89.
125.       10.0              594.        89.
125.       12.5              562.        84.
125.       15.0              441.        66.
125.       20.0              177.        27.
ENDDATA             12
ENDSUBENT           18