O5R, a General-purpose Monte Carlo Neutron Transport Code

O5R, a General-purpose Monte Carlo Neutron Transport Code
Author: D. C. Irving
Publisher:
Total Pages: 224
Release: 1965
Genre: Coding theory
ISBN:
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O5R, a General-purpose Monte Carlo Neutron Transport Code
Language: en
Pages: 224

O5R, a General-purpose Monte Carlo Neutron Transport Code

Authors: D. C. Irving
Categories: Coding theory
Type: BOOK - Published: 1965 - Publisher:

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MCNP, a General Monte Carlo Code for Neutron and Photon Transport
Language: en
Pages:

MCNP, a General Monte Carlo Code for Neutron and Photon Transport

Authors:
Categories:
Type: BOOK - Published: 1979 - Publisher:

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The general-purpose Monte Carlo code MCNP can be used for neutron, photon, or coupled neutron-photon transport, including the capability to calculate eigenvalue
MCNP
Language: en
Pages: 512

MCNP

Authors: Los Alamos Monte Carlo Group
Categories: MCNP (Computer program)
Type: BOOK - Published: 1981 - Publisher:

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MCNP - A GENERAL MONTE CARLO CODE FOR NEUTRON AND PHOTON TRANSPORT.
Language: en
Pages: 0

MCNP - A GENERAL MONTE CARLO CODE FOR NEUTRON AND PHOTON TRANSPORT.

Authors: W. L. Thompson
Categories:
Type: BOOK - Published: - Publisher:

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MCNP
Language: en
Pages:

MCNP

Authors:
Categories:
Type: BOOK - Published: 1985 - Publisher:

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MCNP is a very general Monte Carlo neutron photon transport code system with approximately 250 person years of Group X-6 code development invested. It is extrem