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Journal ArticleDOI

Initial MCNP6 Release Overview

TLDR
High confidence in the MCNP6 code is based on its performance with the verification and validation test suites, comparisons to its predecessor codes, the regression test suite, its code development process, and the underlying high-quality nuclear and atomic databases.
Abstract
MCNP6 is simply and accurately described as the merger of MCNP5 and MCNPX capabilities, but it is much more than the sum of those two computer codes. MCNP6 is the result of five years of effort by ...

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Citations
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Journal ArticleDOI

ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data

TL;DR: The ENDF/B-VII.1 library as mentioned in this paper is the most widely used data set for nuclear data analysis and has been updated several times over the last five years. But the most recent version of the ENDF-B-VI.0 library is based on the JENDL-4.0 standard.
Journal ArticleDOI

ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data

David Brown, +69 more
- 01 Feb 2018 - 
TL;DR: The new ENDF/B-VIII.0 evaluated nuclear reaction data library as mentioned in this paper includes improved thermal neutron scattering data and uses new evaluated data from the CIELO project for neutron reactions on 1 H, 16 O, 56 Fe, 235 U, 238 U and 239 Pu described in companion papers.
Journal ArticleDOI

TENDL: complete nuclear data library for innovative nuclear science and technology

TL;DR: This paper will demonstrate the performance of the latest TENDL releases for different application fields, as well as new approaches for uncertainty quantification based on Bayesian inference methods and possible differential and integral adjustments.
Journal ArticleDOI

Radiation track, DNA damage and response—a review

TL;DR: It is hypothesized that concepts of condensed-matter physics along with the new genomic knowledge and technologies and mechanistic mathematical modeling in conjunction with advances in experimental DNA repair and cell signaling have now provided us with unprecedented opportunities in radiation biophysics to address problems in targeted cancer therapy, and genetic risk estimation in humans.
References
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MCNP-A General Monte Carlo N-Particle Transport Code

TL;DR: In this article, the authors present a practical guide for the use of general-purpose Monte Carlo code MCNP, including several examples and a discussion of the particular techniques and the Monte Carlo method itself.
Journal ArticleDOI

The Monte Carlo method.

TL;DR: In this paper, the authors present a statistical approach to the study of integro-differential equations that occur in various branches of the natural sciences, such as biology and chemistry.
Journal ArticleDOI

ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data

TL;DR: The ENDF/B-VII.1 library as mentioned in this paper is the most widely used data set for nuclear data analysis and has been updated several times over the last five years. But the most recent version of the ENDF-B-VI.0 library is based on the JENDL-4.0 standard.
Book ChapterDOI

The Monte Carlo Method

TL;DR: In this paper, the authors describe the Monte Carlo method for the simulation of grain growth and recrystallization, and present a small subset of the broader use of Monte Carlo methods for which an excellent overview can be found in the book.
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Why is cat6 faster yhan cat5?

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