Integral experiment to test carbon and nitrogen cross sections. Final report, 23 August 1971--15 August 1972
Technical Report
·
OSTI ID:4328176
An integral experiment, designed to provide high sensitivity tests for gamma-ray production and neutron-scattering cross sections, was performed. The experiment is based on the whitesource, pulsed-neutron, time-of-flight method with the sample at the detector end of the flight path. Measurements were made with a single 5 x 5 cm cylindrical NE-213 detector positioned at Pulse-shape discrimination was used to separate neutron and gamma-ray counts. Measured count rates due to secondary gamma rays and scattered neutrons from two sample materials, graphite and liquid nitrogen, are reported here as functions of time and incident neutron energy. Differences between calculated gammaray and neutron count rates and those reported should be readily interpreted in terms of specific, cross section deficiencies at well defined incident neutron energies in the 1.5- to 20-MeV range. (GRA)
- Research Organization:
- Gulf Radiation Technology, San Diego, Calif. (USA)
- NSA Number:
- NSA-29-030712
- OSTI ID:
- 4328176
- Report Number(s):
- AD--768477-2-GA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Integral measurements to test neutron scattering and gamma-ray production cross sections for Be, C, N, H/sub 2/O, and Fe. Final report, Aug 1971--May 1975. [2 to 20 MeV]
Analysis of neutron scattering and gamma-ray production integral experiments on nitrogen for neutron energies from 1 to 15 MeV
Analysis of a neutron scattering and gamma-ray production integral experiment on aluminum for neutron energies from 1 to 15 MeV
Technical Report
·
Mon Jun 02 00:00:00 EDT 1975
·
OSTI ID:7346727
Analysis of neutron scattering and gamma-ray production integral experiments on nitrogen for neutron energies from 1 to 15 MeV
Technical Report
·
Sun Feb 29 23:00:00 EST 1976
·
OSTI ID:4014474
Analysis of a neutron scattering and gamma-ray production integral experiment on aluminum for neutron energies from 1 to 15 MeV
Technical Report
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:5183366
Related Subjects
*CARBON-- NEUTRON REACTIONS
*NEUTRON REACTIONS-- SCATTERING
*NITROGEN-- NEUTRON REACTIONS
CROSS SECTIONS
GRAPHITE
MEV RANGE 01-10
MEV RANGE 10-100
N68351* --Physics (Nuclear
Experimental)--Nuclear Properties & Reactions
6 <= A <= 19--Nuclear Reactions & Scattering
PARTICLE PRODUCTION
PHOTONS
*NEUTRON REACTIONS-- SCATTERING
*NITROGEN-- NEUTRON REACTIONS
CROSS SECTIONS
GRAPHITE
MEV RANGE 01-10
MEV RANGE 10-100
N68351* --Physics (Nuclear
Experimental)--Nuclear Properties & Reactions
6 <= A <= 19--Nuclear Reactions & Scattering
PARTICLE PRODUCTION
PHOTONS