Neutron-induced photon production in MCNP
Description:
An improved method of neutron-induced photon production has been incorporated into the Monte Carlo transport code MCNP. The new method makes use of all partial photon-production reaction data provided by ENDF/B evaluators including photon-production cross sections as well as energy and angular distributions of secondary photons. This faithful utilization of sophisticated ENDF/B evaluations allows more precise MCNP calculations for several classes of coupled neutron-photon problems.
Date:
January 1, 1983
Creator:
Little, R. C. & Seamon, R. E.
Item Type:
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Partner:
UNT Libraries Government Documents Department