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research-article

The Powerful MOC Module in Advanced Neutronics Lattice Code KYLIN-2

[+] Author and Article Information
Xiaoming Chai

State Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China(NPIC) No. 328, Rd. Changshun, Shuangliu, Chengdu
chaixm@163.com

Xiaolan Tu

Nuclear Power Institute of China(NPIC) No. 328, Rd. Changshun, Shuangliu, Chengdu
tuxiaolan2014@126.com

Wei Lu

Nuclear Power Institute of China(NPIC) No. 328, Rd. Changshun, Shuangliu, Chengdu
luwei9s@sina.cn

Zongjian Lu

State Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China(NPIC) No. 328, Rd. Changshun, Shuangliu, Chengdu
317142242@qq.com

Dong Yao

State Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China(NPIC) No. 328, Rd. Changshun, Shuangliu, Chengdu
yaodong_npic@163.com

Qing Li

Nuclear Power Institute of China(NPIC) No. 328, Rd. Changshun, Shuangliu, Chengdu
liqing-npic@126.com

Wenbin Wu

Nuclear Power Institute of China(NPIC) No. 328, Rd. Changshun, Shuangliu, Chengdu
wenbinwu@126.com

1Corresponding author.

ASME doi:10.1115/1.4035934 History: Received September 24, 2016; Revised February 05, 2017

Abstract

Due to powerful geometry treatment capability, Method Of Characteristics (MOC) currently becomes one of best method to solve neutron transport equation. In MOC method, boundary condition treatment, complex geometry representation, and advanced acceleration method are the key techniques to develop a powerful MOC code to solve complex problem. In this paper, we developed a powerful MOC module, which can treat different boundary conditions with two methods. For problems with special border shapes and boundary condition, such as rectangle, 1/8 of square, hexagon, 1/6 of hexagon problems with reflection, rotation, and translation boundary condition, the MOC module adopts periodic tracking method. For problems with general border shapes, the MOC module use ray prolongation method. Meanwhile, graphic user interface based on CAD software is developed to generate the geometry description file. The geometry and mesh can be described and modified correctly and fast. In order to accelerate the MOC transport calculation, the Generalized Coarse Mesh Finite Differential (GCMFD) is used, which can use irregular coarse mesh diffusion method to accelerate the transport equation. The MOC module was incorporated into advanced neutronics lattice code KYLIN-2, which developed by Nuclear Power Institute of China (NPIC) and used to simulate the assembly of current PWR reactor and advanced reactors. The numerical results show that the KYLIN-2 code can be used to calculate 2D neutron transport problems accurately and fast. In future, the KYLIN-2 code will be released and gradually become the main neutron transport lattice code in NPIC.

Copyright (c) 2017 by ASME
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