Local Approach to Fracture of Nuclear Reactor Vessel Model Subjected to Thermal Cycle

• Takagaki Masakazu

  Institute of Industrial Science, University of Tokyo

• Toi Yutaka

  Institute of Industrial Science, University of Tokyo

• Asayama Tai

  Japan Nuclear Cycle Development Institute

Bibliographic Information

Other Title

• 熱サイクルを受ける原子炉容器モデルの局所的破壊解析

Abstract

Local approach to fracture based on continuum damage mechanics and finite element method has been applied to the low-cycle fatigue damage behavior of a nuclear reactor vessel model subjected to thermal cycle. Two parts near the inflow nozzle and the conical body have been analyzed, the calculated results for which have been compared with the existing experimental results.

Journal

• NCTAM papers, National Congress of Theoretical and Applied Mechanics, Japan

  NCTAM papers, National Congress of Theoretical and Applied Mechanics, Japan 55 (0), 271-271, 2006

  National Committee for IUTAM

Keywords

• thermal cycle
• nuclear reactor vessel
• damage

Details

• CRID: 1390282680570030848
• NII Article ID: 130005020439
• DOI: 10.11345/japannctam.55.0.271.0
• Data Source:
  • JaLC
  • CiNii Articles
  • KAKEN
• Abstract License Flag: Disallowed