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	Transient tests on blower trip and rod removal at the HTR-10
	Hu, S. ; Ruipian Wang ; Zuying Gao
	2010-05-10 ; 2010-05-10
关键词	Practical Theoretical or Mathematical/ fission reactor cooling fission reactor safety nuclear criticality safety reactivity (fission reactors)/ helium blower trip control rod removal safety demonstration tests high temperature gas-cooled reactor test module MHTGR primary cooling system transient data anticipated transient without scram tests ATWS reactivity insertion negative temperature coefficient reactor power heat removal levels fuel temperature core heat capacity tripping test helium circulator criticality safety strong negative reactivity feedback effect/ A2843B Cooling and heat recovery in fission reactors A2843D Core control and guidance in fission reactors A2844 Fission reactor protection systems, safety and accidents A2846E Nuclear criticality safety A2850I Gas cooled reactors B8220B Nuclear reactors
中文摘要	Safety demonstration tests on the 10MW high temperature gas-cooled reactor test module (HTR-10) were conducted to verify the inherent safety features of MHTGRs and to obtain the core and primary cooling system transient data for validation of safety analysis codes. Two simulated anticipated transients without scram (ATWS) tests, lose of forced cooling by trip of the helium blower and reactivity insertion via control rod withdrawal were performed. This paper describes the tests with detailed test method, condition and results. Calculated results show that the strongly negative temperature coefficient causes reactor power to closely follow heat removal levels. Maximum fuel temperature changes are limited by the large core heat capacity to below 1230 degrees C during two tests. The test of tripping the helium circulator ATWS test was conducted on October 15, 2003. Although none of 10 control rods was moved, the reactor power immediately decreased due to the negative temperature coefficient. After about 50min, the reactor became criticality again. Finally, the reactor power went to a stable level with about 200kW. The test of reactivity insertion ATWS test was conducted two times. Following the control rod withdrawal, the reactor power increased rapidly, the maximum power level reached to 5037 and 7230kW from the initial power of 3000kW in accordance with reactivity insertion of $ 0.136 and 0.689, respectively. After the reactivity introduced was compensated by means of the strong negative reactivity feedback effect, the reactor went to subcritical and the power decreased. [All rights reserved Elsevier].
语种	英语 ; 英语
出版者	Elsevier ; Netherlands
内容类型	期刊论文
源URL	[http://hdl.handle.net/123456789/23183]
专题	清华大学
推荐引用方式 GB/T 7714	Hu, S.,Ruipian Wang,Zuying Gao. Transient tests on blower trip and rod removal at the HTR-10[J],2010, 2010.
APA	Hu, S.,Ruipian Wang,&Zuying Gao.(2010).Transient tests on blower trip and rod removal at the HTR-10..
MLA	Hu, S.,et al."Transient tests on blower trip and rod removal at the HTR-10".(2010).

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