Computational Methods of Neutron Transport
Computational Methods of Neutron Transport
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发表时间：
1993
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通讯作者：
E. Lewis;W. Miller
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作者：
E. Lewis;W. Miller
这本书提出了一个平衡的概述，主要方法目前可用于获得数值解在中子和伽马射线传输。它侧重于特别适用于反应堆、聚变装置、辐射屏蔽和其他核系统分析中遇到的复杂问题的方法。给出了每种方法的推导过程，说明了如何将输运方程化为适合在数字计算机上求解的代数方程组。从计算机内存、时间要求和精度等方面讨论了这些方法的局限性及其对不同类型问题的适用性。
This books presents a balanced overview of the major methods currently available for obtaining numerical solutions in neutron and gamma ray transport. It focuses on methods particularly suited to the complex problems encountered in the analysis of reactors, fusion devices, radiation shielding, and other nuclear systems. Derivations are given for each of the methods showing how the transport equation is reduced to sets of algebraic equations suitable for solution on a digital computer. The limitations of the methods and their suitability for different classes of problems are discussed in terms of computer memory, time requirements, and accuracy.