Experiment Study on Rod Ejection Accident Hydraulic Control Rod Driving System

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概要

• 論文の詳細を見る

• The rod ejection experiment has been done in the 1:1 experiment loop of the hydraulic control rod driving system (HCRDS) of the 200 MW nuclear heating reactor (NHR-200). The result indicated that under different experiment conditions, the control rod was not ejected when the pressure vessel of the loop lost pressure. Based on the depressurization accident analysis of the NHR-200, performed at the Institute of Nuclear Energy Technology (INET), Tsinghua University, the depressurization rate of experiment is much higher than that of analysis. Thus, the HCRDS has inherent safety and no hidden trouble of rod ejection when the depressurization accident happens.

• 社団法人 日本原子力学会の論文
• 2001-12-25

著者

• Dong Duo

  Institute Of Nuclear Energy Technology Tsinghua University

• ZHENG Yanhua

  Institute of Nuclear and New Energy Technology, Tsinghua University

• WANG Jinhua

  Institute of Computer Science and Engineering, Beijing Jiaotong University

• Wang Jinhua

  Institute Of Nuclear And New Energy Technology The Key Laboratory Of Advanced Reactor Engineering An

• Wang Jinhua

  Institute Of Computer Science And Engineering Beijing Jiaotong University

• Wang Jinhua

  Institute Of Nuclear Energy Techology Tsinghua University

• Zheng Yanhua

  Institute Of Nuclear Energy Technology Tsinghua University

• Zheng Yanhua

  Institute Of Nuclear And New Energy Technology Tsinghua University

• BO Hanliang

  Institute of Nuclear Energy Technology, Tsinghua University

• Bo Hanliang

  Institute Of Nuclear And New Energy Technology The Key Laboratory Of Advanced Reactor Engineering An

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