Experimental Study of the Pressure Discharge Process for the Hydraulic Control Rod Drive System Stepped Cylinder
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概要
- 論文の詳細を見る
The pressure discharge process from the stepped cylinder of the Hydraulic Control Rod Drive System (HCRDS) was studied experimentally in the HCRDS experimental loop for the 200 MW Nuclear Heating Reactor (NHR-200). The results showed that the differential pressure between the outside and the inside of the stepped cylinder increased rapidly to the desired value so that the force induced by the differential pressure which pushes the out tube of stepped cylinder was large enough. Therefore, if the hydraulic control rod were jammed, the pressure could push the hydraulic control rod to overcome the frictional resistance to insert the control rod into the reactor core. The experimental results verified that this design would solve the problem of hydraulic control rod jamming during an accident.
- 社団法人 日本原子力学会の論文
- 2002-12-25
著者
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WANG Jinhua
Institute of Computer Science and Engineering, Beijing Jiaotong University
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Wang Jinhua
Institute Of Nuclear And New Energy Technology The Key Laboratory Of Advanced Reactor Engineering An
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Wang Jinhua
Institute Of Computer Science And Engineering Beijing Jiaotong University
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Wang Jinhua
Institute Of Nuclear Energy Techology Tsinghua University
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BO Hanliang
Institute of Nuclear Energy Technology, Tsinghua University
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ZHENG Wenxiang
Institute of Nuclear and New Energy Technology, the Key Laboratory of Advanced Reactor Engineering a
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Zheng Wenxiang
Institute Of Nuclear And New Energy Technology The Key Laboratory Of Advanced Reactor Engineering An
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Bo Hanliang
Institute Of Nuclear And New Energy Technology The Key Laboratory Of Advanced Reactor Engineering An
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Zheng Wenxiang
Institute Of Nuclear Energy Technology Tsinghua University
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