MCN: a neutron Monte Carlo code

Cashwell, E.D.; Neergaard, Jon R.; Taylor, William M.; Turner, G.D.

doi:10.2172/4497077

Cited by 22 publications

(27 citation statements)

References 2 publications

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“…3 For the nonhssionable samples, the correction was applied to the data as a function of gamma-ray energy. In general, a nonelaatic collision in any of the samples reduces ihe neutron energy to such an extent that a second nonelastic collision cannot produce highenergy gamma rays.…”

Section: Multiple Scatteringmentioning

confidence: 99%

Fourteen-MeV, neutron-induced gamma-ray production cross sections

Drake¹,

Arthur²,

Silbert³

1974

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Section: Multiple Scatteringmentioning

confidence: 99%

Fourteen-MeV, neutron-induced gamma-ray production cross sections

Drake¹,

Arthur²,

Silbert³

1974

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“…It is expected thct :he tungsten measurement will also provide a severer iest of the Monte Carlo Code, MCN, end of the cross sections used, then will iron. 2 Except for the detectors, the neutron and gamma-ray measurements were made with identical experimental arrangements including neutron source, spherical samples, and collimators.…”

Section: H(tn)mentioning

confidence: 99%

“…Neutron and gamma-ray spectra emitted bom spheres of iron and tungsten have been measured using the 2 …”

Section: Introductionmentioning

confidence: 99%

Measurements of neutron and gamma-ray spectra from iron and tungsten spheres bombarded with neutrons from the $sup 2$H(t,n)$sup 4$He reaction

Arthur¹,

Auchampaugh²,

Drake³

1974

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Gamma-ray and neutron spectra produced by pulsed sources of 2 H{t,n)*He neutrons in the centers of iron and tungsten spheres have been measured using time-of-flight techniques. Identical experimental arrangements, except for detectors, were used for both neutron and gamma-ray measurements. Results of the measurements are presented in formats that can be compared easily with Monte Carlo calculations.

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“…During the 1950s -1960s, a number of special-purpose Monte Carlo codes were developed at LANL, including MCS, MCN, MCP, and MCG. These methods eventually found their way into a code called MCNG, which was first created in 1973 by merging a three dimensional neutron transport code MCN (Cashwell et al, 1972), with the gamma transport code MCG (Cashwell et al, 1973). In 1977 MCNG was merged with MCP, a Monte Carlo photon code with detailed physics treatment down to 1 keV, to more accurately model neutron-photon interactions.…”

Section: Introductionmentioning

confidence: 99%

Features of MCNP6

Goorley

James

Booth

et al. 2016

Annals of Nuclear Energy

130

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a b s t r a c t MCNP6 can be described as the merger of MCNP5 and MCNPX capabilities, but it is much more than the sum of these two computer codes. MCNP6 is the result of six years of effort by the MCNP5 and MCNPX code development teams. These groups of people, residing in Los Alamos National Laboratory's X Computational Physics Division, Monte Carlo Codes Group (XCP-3) and Nuclear Engineering and Nonproliferation Division, Radiation Transport Modeling Team (NEN-5) respectively, have combined their code development efforts to produce the next evolution of MCNP. While maintenance and major bug fixes will continue for MCNP5 1.60 and MCNPX 2.7.0 for upcoming years, new code development capabilities only will be developed and released in MCNP6. In fact, the initial release of MCNP6 contains numerous new features not previously found in either code. These new features are summarized in this document. Packaged with MCNP6 is also the new production release of the ENDF/B-VII.1 nuclear data files usable by MCNP. The high quality of the overall merged code, usefulness of these new features, along with the desire in the user community to start using the merged code, have led us to make the first MCNP6 production release: MCNP6 version 1. High confidence in the MCNP6 code is based on its performance with the verification and validation test suites, comparisons to its predecessor codes, our automated nightly software debugger tests, the underlying high quality nuclear and atomic databases, and significant testing by many beta testers.

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MCN: a neutron Monte Carlo code

Cited by 22 publications

References 2 publications

Fourteen-MeV, neutron-induced gamma-ray production cross sections

Fourteen-MeV, neutron-induced gamma-ray production cross sections

Measurements of neutron and gamma-ray spectra from iron and tungsten spheres bombarded with neutrons from the $sup 2$H(t,n)$sup 4$He reaction

Features of MCNP6

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