An Integrity Evaluation Method of the Pressure Vessel of Nuclear Reactors Under Pressurized Thermal Shock

スポンサーリンク

概要

• 論文の詳細を見る

• The present paper proposes a new algorithm of the integrity evaluation of the pressure vessel of nuclear reactors under pressurized thermal shock, PTS. This method enables us to perform an effective evaluation by superimposing proposed stress intensity factor transient curves and fracture toughness transient curves, and is superior to conventional methods in the following points : (1) It is easy to obtain an overall view of the result of the PTS event for the variations of several parameters. (2) It is possible to evaluate a safety margin for irradiation embrittlement. (3) It enable the construction of a expert-interactive evaluation system. In addition, the results shows that we can execute a safety assurance test using a flat plate model with the same thickness as that of the real plant.

• 一般社団法人日本機械学会の論文
• 1988-10-15

著者

• Okamura H

  Univ. Tokyo Tokyo Jpn

• MATSUBARA Masaaki

  Central Research Institute of Electric Power Industry

• OKAMURA Hiroyuki

  University of Tokyo

関連論文

• An Integrity Evaluation Method of the Pressure Vessel of Nuclear Reactors Under Pressurized Thermal Shock

スポンサーリンク