Development of core fuel management code system for CANDU reactor based on coupled neutronics and thermal-hydraulic advanced nodal method

Author:

Huo Xiaodong,Xie Zhongsheng,Liao Chengkui

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference14 articles.

1. Benchmark problem book ANL-7416,1985

2. Dastur, A.R., Buss, D.B., 1983. MULTICELL-A 3-D program for the simulation of reactivity devices in CANDU. AECL Report, AECL-7544.

3. Douglas, S.R., 2000. WIMS-AECL Release 2-5d users manual. COG-94-52 (Rev. 4).

4. Interface current techniques for multi-dimensional reactor calculations;Finnemann;Atomkernenergie (ATKE) Bd.30,1977

5. Liao Chengkui, 2002. Study on numerical solution for three dimensional nodal space-time neutron kinetic equations and coupled neutronics/thermal-hydraulic core transient analysis. Phd. thesis, Xi'an Jiaotong University, China.

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