TACR热传输系统热工水力瞬态分析

doi:10.11889/j.0253-3219.2017.hjs.40.080601

Nuclear Techniques ›› 2017, Vol. 40 ›› Issue (8): 80601-080601.doi: 10.11889/j.0253-3219.2017.hjs.40.080601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles Next Articles

Thermal-hydraulic transient analysis for heat transport system of thorium-based advanced CANDU reactor

WEI Shiying¹, WANG Wei², WANG Chenglong¹, TIAN Wenxi¹, QIU Suizheng¹, SU Guanghui¹

1. School of Energy and Power Engineering, Xi'an Jiaotong University, Xi'an 710049, China;
2. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610041, China

Received:2017-01-03 Revised:2017-04-10 Online:2017-08-10 Published:2017-08-11
Supported by:
Supported by International Science&Technology Cooperation Program of China (No.2014DFA60650),China Postdoctoral Science Foundation (No.BX201600124)

Abstract

Abstract: Background: The utilization of thorium in reactors is of great significance to alleviate the shortage of nuclear fuel and Canadian deuterium uranium (CANDU) reactor is one of the best choice to be introduced in thorium fuel cycles. The abundant thorium deposit and rich experience in operating Qinshan phase Ⅲ laid a foundation for researches on thorium-based advanced CANDU reactor (TACR) in China. Purpose:To support the international cooperative study on TACR between Canada and China and lay a foundation for self-development of the software for CANDU thermal hydraulic analysis in our country, it is necessary to develop analysis code in order to evaluate thermal hydraulic performance of CANDU reactor heat transport system. Methods: In this study, a CANDU thermal hydraulic transient analysis code (CANTHAC) was developed using FORTRAN language and used to analysis the transient performance of TACR heat transport system. The full power steady state, steam generator (SG) feed water temperature reduction accident and complete loss of flow accident were simulated. Results: The steady state results by CANTHAC were in good agreement with the rated value designed by Tsinghua University and the maximum calculation error was less than 2%, which is acceptable. The calculation results of SG feed water temperature reduction accident and complete loss of flow accident shown that key parameters including the fuel temperature and system pressure do not exceed specified limits and satisfy the safety criteria. Conclusion: The steady state results agree well with the rated value and the transient results are reasonable, which preliminarily evaluate the validity of the transient analysis code. Since the code was modularized, it would be convenient for further modification and application.

Key words: TACR, Heat transport system, Thermal-hydraulic, Transient analysis

CLC Number:

TL333

WEI Shiying, WANG Wei, WANG Chenglong, TIAN Wenxi, QIU Suizheng, SU Guanghui. Thermal-hydraulic transient analysis for heat transport system of thorium-based advanced CANDU reactor[J].Nuclear Techniques, 2017, 40(8): 80601-080601.

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Thermal-hydraulic transient analysis for heat transport system of thorium-based advanced CANDU reactor

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