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Contributon Monte Carlo. [Application in MCNP code]

Authors: Dubi, A.; Gerstl, S.A.W.;

Contributon Monte Carlo. [Application in MCNP code]

Abstract

The contributon Monte Carlo method is based on a new recipe to calculate target responses by means of volume integral of the contributon current in a region between the source and the detector. A comprehensive description of the method, its implementation in the general-purpose MCNP code, and results of the method for realistic nonhomogeneous, energy-dependent problems are presented. 23 figures, 10 tables.

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United States
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Keywords

Computer Calculations, Computer Codes, Neutral-Particle Transport, Sodium, Energy Dependence, 73 Nuclear Physics And Radiation Physics, Elements, Alkali Metals, Radiation Transport 654001* -- Radiation & Shielding Physics-- Radiation Physics, Metals, Neutron Transport, Shielding Calculations & Experiments, Pipes, M Codes, 654003 -- Radiation & Shielding Physics-- Neutron Interactions With Matter, Monte Carlo Method, Transport Theory, Calculation Methods

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selected citations
These citations are derived from selected sources.
This is an alternative to the "Influence" indicator, which also reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).
BIP!Citations provided by BIP!
popularity
This indicator reflects the "current" impact/attention (the "hype") of an article in the research community at large, based on the underlying citation network.
BIP!Popularity provided by BIP!
influence
This indicator reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).
BIP!Influence provided by BIP!
impulse
This indicator reflects the initial momentum of an article directly after its publication, based on the underlying citation network.
BIP!Impulse provided by BIP!
0
Average
Average
Average
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