Certification of MCNP Version 4A for WHC computer platforms. Revision 7 | Zendy

L.L. Carter | Zendy

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Certification of MCNP Version 4A for WHC computer platforms. Revision 7

Author(s) -

L.L. Carter

Publication year - 1995

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/71572

Subject(s) - torus , monte carlo method , neutron , code (set theory) , eigenvalues and eigenvectors , degree (music) , bounded function , neutron transport , nuclear physics , computer science , physics , statistical physics , mathematics , geometry , mathematical analysis , programming language , statistics , quantum mechanics , set (abstract data type) , acoustics

MCNP is a general-purpose Monte Carlo code that can be used for neutron, photon, or coupled neutron/photon transport, including the capability to calculate eigenvalues for critical systems. The code treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces, and some special fourth-degree surfaces (elliptical tori)

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