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)

概要

論文の詳細を見る
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.
社団法人日本機械学会の論文
2004-06-22