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Research Papers

Development of SNTA Code System for SCWR Core Steady-State Analysis

[+] Author and Article Information
Lianjie Wang

Science and Technology on Reactor System
Design Technology Laboratory,
Nuclear Power Institute of China,
No. 328, Section 1, Changshun Avenue,
Shuangliu County,
Chengdu 610213, China
e-mail: wanglianjie@npic.ac.cn

Wenbo Zhao

Science and Technology on Reactor System
Design Technology Laboratory,
Nuclear Power Institute of China,
No. 328, Section 1, Changshun Avenue,
Shuangliu County,
Chengdu 610213, China
e-mail: zhaowenbo.npic@gmail.com

Ping Yang

Science and Technology on Reactor System
Design Technology Laboratory,
Nuclear Power Institute of China,
No. 328, Section 1, Changshun Avenue,
Shuangliu County,
Chengdu 610213, China
e-mail: pyangxjtu@gmail.com

Yongqiang Ma

Science and Technology on Reactor System
Design Technology Laboratory,
Nuclear Power Institute of China,
No. 328, Section 1, Changshun Avenue,
Shuangliu County,
Chengdu 610213, China
e-mail: myq103@126.com

Di Lu

Science and Technology on Reactor System
Design Technology Laboratory,
Nuclear Power Institute of China,
No. 328, Section 1, Changshun Avenue,
Shuangliu County,
Chengdu 610213, China
e-mail: ludyhao@126.com

1Corresponding author.

Manuscript received May 23, 2016; final manuscript received October 11, 2016; published online March 1, 2017. Assoc. Editor: Mark Anderson.

ASME J of Nuclear Rad Sci 3(2), 021005 (Mar 01, 2017) (6 pages) Paper No: NERS-16-1050; doi: 10.1115/1.4035334 History: Received May 23, 2016; Revised October 11, 2016

A coupled neutronics/thermal-hydraulics (N/T) three-dimensional code system SNTA is developed for supercritical water-cooled reactor (SCWR) core steady-state analysis by modular coupling the improved neutronics nodal methodological code and SCWR thermal-hydraulic subchannel code. The appropriate outer iteration coupling method and self-adaptive relaxation factor are proposed for enhancing convergence, stability, and efficiency of coupled N/T calculation. The steady-state analysis for the CSR1000 core is applied to verify SNTA. The results calculated by SNTA agreed well with those by CASIR and SRAC. SNTA is more efficient than CASIR and SRAC, where the neutronics modules are based on the finite-difference method. The numeric results show that SNTA can be applied to SCWR core steady-state analysis and core concept design.

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References

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Figures

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Fig. 1

Flow chart of neutronics and thermal-hydraulics coupling for steady state

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Fig. 2

CSR1000 fuel assembly

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Fig. 3

CSR1000 core configuration

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Fig. 4

Water flow scheme of CSR1000

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Fig. 5

Comparison of core axial power distributions

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Fig. 6

Comparison of quarter core radial power distributions

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Fig. 7

Comparison of the first flow path coolant axial density distributions

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Fig. 8

Comparison of the second flow path coolant axial density distributions

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Fig. 9

Comparison of core outlet coolant density distributions (second flow path)

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