EPJ Web Conf.
Volume 153, 2017ICRS-13 & RPSD-2016, 13th International Conference on Radiation Shielding & 19th Topical Meeting of the Radiation Protection and Shielding Division of the American Nuclear Society - 2016
|Number of page(s)||7|
|Section||6. Calculation Methods Monte Carlo & Deterministic|
|Published online||25 September 2017|
Research on Primary Shielding Calculation Source Generation Codes
1 Shanghai Nuclear Engineering Research and Design Institute Hongcao Road No. 29, Shanghai, China
2 Institute of Applied Physics and Computational Mathematics Fenghao East Road No. 2, Beijing, China
* Corresponding author: email@example.com
Published online: 25 September 2017
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 J Monte Carlo Transport (JMCT) code, and a source particle sample code is deveoped 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 θ z geometry for the J Discrete Ordinate Transport (JSNT) 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.
© The Authors, published by EDP Sciences, 2017
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