動力・エネルギー技術の最前線講演論文集 : シンポジウム
Online ISSN : 2424-2950
セッションID: NP2-11
会議情報
改良型沸騰水型軽水炉下部プレナム内の流動評価技術(NP2 軽水炉の設計・建設技術)
高橋 志郎曽根田 秀夫安田 賢一椎名 孝次福田 俊彦水谷 淳渡邉 勝信田嶋 智子
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会議録・要旨集 フリー

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Reactor internal pumps (RIPs) are used in the advanced boiling water reactor (ABWR) nuclear power plants to circulate the reactor coolant in the reactor pressure vessel. Control rod drive housings (CRDHs) and control rod guide tubes (CRGTs) in the lower plenum were subjected to RIP discharge flow. Fluid force acting on those structures in the lower plenum must be evaluated in the next ABWR in which lower plenum structures have been improved from the current design. Computational fluid dynamics (CFD) analysis is expected to evaluate the fluid force acting on those structures. The 5 RIPs sector models of the reactor lower plenum were simulated to investigate the fluid force in the present study. Fluctuating fluid forces were calculated based on the velocity distribution obtained from the CFD analysis. Fluctuating fluid forces were applied to the structural models and its FIV stress was calculated by the vibration analysis. As a result, flow in the lower plenum went along the RPV bottom and this flow was desirable for structures. Remarkable fluid force acting on structures was not observed in the ABWR lower plenum.
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© 2004 一般社団法人 日本機械学会
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