Verification of Three Dimensional Neutronics and Thermal-Hydraulic Coupled Code With RIA Benchmarks

LIU Yu; LI Feng; ZHANG Hong; ZHANG Yu; JIA Bao-shan

doi:10.7538/yzk.2010.44.11.1328

Atomic Energy Science and Technology > 2010 > 44(11): 1328-1334. > DOI: 10.7538/yzk.2010.44.11.1328

LIU Yu, LI Feng, ZHANG Hong, ZHANG Yu, JIA Bao-shan. Verification of Three Dimensional Neutronics and Thermal-Hydraulic Coupled Code With RIA Benchmarks[J]. Atomic Energy Science and Technology, 2010, 44(11): 1328-1334. DOI: 10.7538/yzk.2010.44.11.1328

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Verification of Three Dimensional Neutronics and Thermal-Hydraulic Coupled Code With RIA Benchmarks

1.
Department of Engineering Physics, Tsinghua University, Beijing 100084, China
2.
State Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China, Chengdu 610041, China

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Received Date: December 31, 1899
Revised Date: December 31, 1899

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Based on sub-channel code COBRA-Ⅳ and neutron kinetics code NLSANMT, a three dimensional neutronics and thermal-hydraulic coupled code C4/NK was developed. In order to verify the coupled code, two typical reactivity initiated accidents (RIA): NEACRP control rod ejection benchmark and uncontrolled rods withdrawal benchmark at zero power, were calculated. The comparison of results with the reference solutions and other coupled codes shows that the C4/NK code has good accuracy and can correctly simulate the neutronics and thermal-hydraulic feedback phenomena during the transient.

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[1]	WHEELER C L, STEWART C W, CENA R J, et al. COBRA-Ⅳ-Ⅰ: An interim version of COBRA for thermal-hydradic analysis of rod bundle nuclear fuel elements and cores, BNWL-1963[R]. Richland, WA, USA：Pacific Northwest Laboratory, 1976.
[2]	廖承奎. 三维节块中子动力学方程组的数值解法及物理与热工-水力耦合瞬态过程的数值计算的研究[D]. 西安：西安交通大学，2002.
[3]	FINNEMANN H, GALATI A. NEACRP 3-D LWR core transient benchmark specification，OECD/NEA, NEACRP-L-335 (Revision 1)[R]. [S.l.] : OECD/NEA, 1991.
[4]	FINNEMANN H, BAUER H, GALATI A, et al. Results of LWR core transient benchmarks, NEA/NSC/DOC(93)25[R]. [S.l.] : OECD/NEA, 1993.
[5]	FRAIKIN R, FINNEMANN H. NEA-NSC 3-D/1-D PWR core transient benchmark uncontrolled withdrawal of control rods at zero power, NEA/NSC(93)9 [R]. [S.l.] : OECD/NEA, 1993.
[6]	FRAIKIN R. PWR benchmark on uncontrolled rods withdrawal at zero power final report, NEA/NSC/DOC(96)20[R]. [S.l.] : OECD/NEA, 1997.

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Verification of Three Dimensional Neutronics and Thermal-Hydraulic Coupled Code With RIA Benchmarks

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