2417 改良型加圧水型軽水炉炉内流動解析コード改良試験流体圧力変動評価コードの改良
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概要
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In an advanced pressurized water reactor, a radial reflector is newly adopted. It is necessary to improve safety analysis computer codes for nuclear regulations in order to evaluate coolability and flow-induced vibration of the radial reflector. This paper presents the development and application of the computational fluid dynamics code : IMPACT code to estimate the flow-induced vibration on the core barrel.
- 一般社団法人日本機械学会の論文
- 2000-07-31