HYSYS软件在反应堆系统仿真中的应用探索

doi:10.11889/j.0253-3219.2016.hjs.39.060602

Nuclear Techniques ›› 2016, Vol. 39 ›› Issue (6): 60602-060602.doi: 10.11889/j.0253-3219.2016.hjs.39.060602

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles

Applied exploration of HYSYS code in reactor system simulation

ZHENG Haiwei^1,2, E Yanzhi^1,2, TANG Yanze³, FU Yao¹, WANG Naxiu¹

1 Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus, Shanghai 201800, China;
2 University of Chinese Academy of Sciences, Beijing 100049, China;
3 Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China

Received:2016-03-07 Revised:2016-03-22 Online:2016-06-10 Published:2016-06-12
Supported by:
Supported by National Natural Science Foundation of China (No.91326201), Strategic Priority Program of Chinese Academy of Sciences (No.XDA02001002)

Abstract

Abstract:

Background: The system code can be used to simulate the effects of the whole system with different operation conditions, which plays an important role in dynamic analysis and safety study. As a world-known modeling tool for process simulation and optimization of oil and gas, Aspen HYSYS has the ability of secondary development for nuclear reactor simulation. Purpose: The aim is to make the coupling of HYSYS and point reactor model and verify its efficiency. Methods: Based on implanted and modified molten salt properties, HYSYS can show the features of molten salt accurately. A dynamic link library is built based on the point reactor model. Then the DLL (Dynamic Link Library) is called by HYSYS to calculate the reactivity which is caused by changes of operation conditions. Some operating conditions of thorium molten salt reactor are simulated and then compared with RELAP5. Results: The results of HYSYS is in good agreement with that of RELAP5. Conclusion: The coupled code is available in simulating molten salt-cooled system.

Key words: Molten salt reactor, HYSYS, Coupling, System simulation

CLC Number:

TL333

ZHENG Haiwei, E Yanzhi, TANG Yanze, FU Yao, WANG Naxiu. Applied exploration of HYSYS code in reactor system simulation[J].Nuclear Techniques, 2016, 39(6): 60602-060602.

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Applied exploration of HYSYS code in reactor system simulation

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