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	Post-test analysis of helium circulator trip without scram at 3 MW power level on the HTR-10
	Chen, F. ; Dong, Y. ; Zhang, Z. ; Zheng, Y. ; Shi, L. ; Hu, S.
	2010-10-12 ; 2010-10-12
关键词	HIGH-TEMPERATURE REACTOR SAFETY DEMONSTRATION TESTS ENGINEERING TEST REACTOR THERMAL RESPONSE DESIGN-FEATURES CORE Nuclear Science & Technology
中文摘要	Safety demonstration tests were conducted on the 10MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) to verify the inherent safety characteristics of modular High Temperature Gas-cooled Reactors (HTGRs) as well as to obtain the transient data of reactor core and primary cooling system for validation of HTGR safety analysis models and codes. As one of these safety demonstration tests, a simulated anticipated transient without scram (ATWS) test called loss of forced cooling by tripping the helium circulator without reactor scram was carried out at 3 MW power level on October 15, 2003. This paper simulates and analyzes the power transient and the thermal response of the reactor during the test by using the THERMIX code. The analytical results are compared with the test data for validation of the code. Owing to the negative temperature coefficient of reactivity, the reactor undergoes a self-shut down after the stop of the helium circulator; the subsequent phenomena such as the recriticality and power oscillations are also studied. During the test a natural circulation loop of helium is established in the core and the other coolant channels and its consequent thermal response such as the temperature redistribution is investigated. In addition, temperatures of the measuring points in the reactor internals are calculated and compared with the measured values. Satisfactory agreements obtained from the comparison demonstrate the basic applicability and reasonability of the THERMIX code for simulating and analyzing the helium circulator trip ATWS test. With respect to the safety features of the HTR-10, it is of most importance that the maximum fuel center temperature during the test is always lower than 1600 degrees C which is the limited value for the HTGR. (C) 2009 Elsevier B.V. All rights reserved.
语种	英语 ; 英语
出版者	ELSEVIER SCIENCE SA ; LAUSANNE ; PO BOX 564, 1001 LAUSANNE, SWITZERLAND
内容类型	期刊论文
源URL	[http://hdl.handle.net/123456789/79371]
专题	清华大学
推荐引用方式 GB/T 7714	Chen, F.,Dong, Y.,Zhang, Z.,et al. Post-test analysis of helium circulator trip without scram at 3 MW power level on the HTR-10[J],2010, 2010.
APA	Chen, F.,Dong, Y.,Zhang, Z.,Zheng, Y.,Shi, L.,&Hu, S..(2010).Post-test analysis of helium circulator trip without scram at 3 MW power level on the HTR-10..
MLA	Chen, F.,et al."Post-test analysis of helium circulator trip without scram at 3 MW power level on the HTR-10".(2010).

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