Validation and Application of MCNP and TORT Source Generation Codes

被引：1

作者：

Zheng, Zheng ^{[1
]}

Mei, Qiliang ^{[1
]}

Li, Hui ^{[1
]}

机构：

[1] Shanghai Nucl Engn Res & Design Inst, Hongcao Rd 29, Shanghai, Peoples R China

来源：

INTERNATIONAL YOUTH NUCLEAR CONGRESS 2016, IYNC2016 | 2017年 / 127卷

关键词：

primary shielding calculation; Monte Carlo method; Discrete Ordinate method; source generation code;

D O I：

10.1016/j.egypro.2017.08.127

中图分类号：

TE [石油、天然气工业]; TK [能源与动力工程];

学科分类号：

0807 ; 0820 ;

摘要：

Primary Shielding Calculation (PSC) plays an important role in reactor shielding design and analysis. In order to facilitate PSC, a source generation code is developed to generate cumulative distribution functions (CDF) for the source particle sample code of the MCNP code, and a source particle sample code is developed to sample source particle directions, types, coordinates, energy and weights from the CDFs. A source generation code is developed to transform three dimensional (3D) power distributions in xyz geometry to source distributions in r theta z geometry for the TORT code. Validation on PSC model of Qinshan No.1 nuclear power plant (NPP), CAP1400 and CAP1700 reactors are performed. Numerical results show that the theoretical model and the codes are both correct. (C) 2017 The Authors. Published by Elsevier Ltd.

引用

页码：255 / 263

页数：9

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