Evaluation of MONJU Core Damage Risk with Change of AOT Using Probabilistic Method

スポンサーリンク

概要

• 論文の詳細を見る

• MONJU is a sodium-cooled, loop-type prototype fast breeder reactor with three primary cooling loops which can supply 280 MW of electricity. Limiting conditions of operation (LCO) defined in the safety regulations in MONJU given the allowed outage time (AOT) are evaluated using a PSA technique. The result indicates the possibility of limit extension and some prospects that we should examine.

著者

• Kurisaka Kenichi

  Safety Evaluation Group Fbr System Engineering Unit Advanced Nuclear System Research And Development

• Sotsu Masutake

  Plant Technology Assessment Group Fbr Plant Engineering Center Japan Atomic Energy Agency

関連論文

• Evaluation of MONJU Core Damage Risk with Change of AOT Using Probabilistic Method
• Assessment of FBR MONJU Accident Management Reliability in Causing Reactor Trips
• Evaluation of MONJU Core Damage Risk due to Control Rod Function Failure

スポンサーリンク