Best Estimated and Conservative Analyses for a Feedwater Pipe Break Accident of an Integral Type Reactor

スポンサーリンク

概要

• 論文の詳細を見る

• An integral type reactor, which is an innovative design to achieve a high degree of safety, is currently being developed at the Korea Atomic Energy Research Institute. A feedwater pipe break accident is one of the most important accidents regarding the safety of an integral type reactor. A best estimated calculation, a conservative calculation, and a parameter study for a feedwater pipe break have been carried out. The sensitivity analysis in this paper performed is to establish the parameters which greatly affect the feedwater pipe break accident. A power level, an initial system pressure, a moderator reactivity coefficient and a break size are the major parameters which maximize a system pressure. The important function that must operate following a feedwater pipe break accident is an opening of the pilot operated safety relief valves, and an initiation of the passive residual heat removal system. The integral reactor safety systems function properly and thus secure the reactor to a safe condition with respect to the safety parameters.

• 一般社団法人 日本原子力学会の論文
• 2006-12-25

著者

• Zee Sung-quun

  Reactor Engineering Department Korea Atomic Energy Research Institute

• Chung Young-jong

  Fluid Engineering Research Team Korea Atomic Energy Research Institute

• Kim Soo

  Fluid System Engineering Department Korea Atomic Energy Research Institute

• Kim Hee-cheol

  Fluid System Engineering Department Korea Atomic Energy Research Institute

• Chung Young-jong

  Fluid System Engineering Department Korea Atomic Energy Research Institute

関連論文

• A Study on the Vortex Shedding and Lock-on behind a Square Cylinder in an Oscillatory Incoming Flow
• Best Estimated and Conservative Analyses for a Feedwater Pipe Break Accident of an Integral Type Reactor

スポンサーリンク