Seismic Analysis of Hydraulic Control Rod Driving System
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概要
- 論文の詳細を見る
A simplified mathematical model was developed for the Hydraulic Control Rod Driving System (HCRDS) of a 200 MW nuclear heating reactor, which incorporated the design of its chamfer-hole step cylinder, to analyze its seismic response characteristics. The control rod motion was analyzed for different sine-wave vibration loadings on platform vibrator. The vibration frequency domain and the minimum acceleration amplitude of the control rod needed to cause the control rod to step to its next setting were compared with the design acceleration amplitude spectrum. The system design was found to be safety within the calculated limits. The safety margin increased with increasing frequency.
- 社団法人 日本原子力学会の論文
- 2002-12-25
著者
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Dong Duo
Institute Of Nuclear Energy Technology Tsinghua University
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ZHENG Yanhua
Institute of Nuclear and New Energy Technology, Tsinghua University
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Zheng Yanhua
Institute Of Nuclear Energy Technology Tsinghua University
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Zheng Yanhua
Institute Of Nuclear And New Energy Technology Tsinghua University
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BO Hanliang
Institute of Nuclear Energy Technology, Tsinghua University
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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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