The MCNPX Monte Carlo Radiation Transport Code
The MCNPX Monte Carlo Radiation Transport Code
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MCNPX 蒙特卡罗辐射传输代码
DOI：
10.1063/1.2720459
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发表时间：
2007
期刊：
影响因子：
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通讯作者：
D. B. Pelowitz
中科院分区：
文献类型：
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作者：
L. Waters;G. Mckinney;J. W. Durkee;M. Fensin;J. Hendricks;M. James;R. Johns;D. B. Pelowitz
MCNPX(蒙特卡罗N粒子扩展)是一个通用的蒙特卡罗辐射输运程序，具有34个粒子和轻离子的三维几何和连续能量输运。它包含灵活的来源和计数选项、交互式图形以及对顺序和多处理计算机平台的支持。MCNPX基于MCNP4c，并已升级到大多数MCNP5功能。MCNP是一种高度稳定的代码跟踪中子，
光子和电子，并使用评估的核数据库中的低能相互作用概率。MCNPX已经将这一基础扩展到一系列全面的粒子和轻离子，重离子传输正在开发中。已包括模型来计算库不可用时的交互概率。最近增加的内容集中在剩余核衰变的时间演化上，允许计算形变和延迟粒子发射。MCNPX现在是一个动态范围很大的代码，出色的中子学能力为模拟实验粒子物理感兴趣的设备提供了新的机会，特别是量热法。本文描述了当前MCNPX版本2.6.C的功能，并讨论了正在进行的代码开发。
MCNPX (Monte Carlo N‐Particle eXtended) is a general‐purpose Monte Carlo radiation transport code with three‐dimensional geometry and continuous‐energy transport of 34 particles and light ions. It contains flexible source and tally options, interactive graphics, and support for both sequential and multi‐processing computer platforms. MCNPX is based on MCNP4c and has been upgraded to most MCNP5 capabilities. MCNP is a highly stable code tracking neutrons,
photons and electrons, and using evaluated nuclear data libraries for low‐energy interaction probabilities. MCNPX has extended this base to a comprehensive set of particles and light ions, with heavy ion transport in development. Models have been included to calculate interaction probabilities when libraries are not available. Recent additions focus on the time evolution of residual nuclei decay, allowing calculation of transmutation and delayed particle emission. MCNPX is now a code of great dynamic range, and the excellent neutronics capabilities allow new opportunities to simulate devices of interest to experimental particle physics, particularly calorimetry. This paper describes the capabilities of the current MCNPX version 2.6.C, and also discusses ongoing code development.