Published 1983 | Version v1
Report Restricted

Neutron-induced photon production in MCNP

Creators

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

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE83011173.

Files

Restricted

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Additional details

Publishing Information

Imprint Pagination
12 p.
Report number
LA-UR--83-1123

Conference

Title
6. international conference on radiation shielding.
Dates
16-20 May 1983.
Place
Tokyo (Japan).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
14782064
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ANGULAR DISTRIBUTION; COMPUTER CALCULATIONS; CROSS SECTIONS; ENERGY SPECTRA; MONTE CARLO METHOD; NEUTRON REACTIONS; NEUTRON TRANSPORT; PHOTON TRANSPORT; TRANSPORT THEORY
Descriptors DEC
BARYON REACTIONS; DISTRIBUTION; HADRON REACTIONS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR REACTIONS; NUCLEON REACTIONS; RADIATION TRANSPORT; SPECTRA

Optional Information

Secondary number(s)
CONF-830538--3.