4.5 Article Proceedings Paper

Capabilities overview of the MORET 5 Monte Carlo code

期刊

ANNALS OF NUCLEAR ENERGY
卷 82, 期 -, 页码 74-84

出版社

PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.anucene.2014.08.022

关键词

MORET; Monte Carlo; Neutron transport; Criticality; Reactor modeling; Validation

向作者/读者索取更多资源

The MORET code is a simulation tool that solves the transport equation for neutrons using the Monte Carlo method. It allows users to model complex three-dimensional geometrical configurations, describe the materials, define their own tallies in order to analyse the results. The MORET code has been initially designed to perform calculations for criticality safety assessments. New features has been introduced in the MORET 5 code to expand its use for reactor applications. This paper presents an overview of the MORET 5 code capabilities, going through the description of materials, the geometry modeling, the transport simulation and the definition of the outputs. (C) 2014 Elsevier Ltd. All rights reserved.

作者

我是这篇论文的作者
点击您的名字以认领此论文并将其添加到您的个人资料中。

评论

主要评分

4.5
评分不足

次要评分

新颖性
-
重要性
-
科学严谨性
-
评价这篇论文

推荐

暂无数据
暂无数据