Concepedia

Recent Japanese research activities on probabilistic fracture mechanics for pressure vessel and piping of nuclear power plant

Yasuhiro Kanto, Kunio Onizawa, H. Machida, Yoshihiro Isobe, S. Yoshimura

International Journal of Pressure Vessels and Piping · 2009 · 14 citations · 2 references

Concepts

EngineeringNuclear EngineeringComputational MechanicsNuclear MaterialsNuclear Safety AnalysisFracture CharacterizationFracture GeometryFracture InitiationFracture MechanicsFracture PropagationProbabilistic Safety AssessmentComputational Fracture MechanicsFracture AssessmentFracture CriterionFracture Mechanics ExperimentsFracture Mechanics SimulationPressure Vessel FailureProbabilistic Fracture MechanicsReactor Pressure Vessel Failure

References

2

Development of Probabilistic Fracture Mechanics Analysis Code PASCAL ver.2 for Reactor Pressure Vessel

Kazuya Osakabe, Kunio Onizawa, Katsuyuki Shibata et al. · Transactions of the Atomic Energy Society of Japan · 2007 · 13 citations · Full text

Engineering, Materials Engineering, Nuclear Engineering +17

Reliability Assessment of PLR Piping Based on Domestic SCC Data

Hideo MACHIDA · Volume 1: Codes and Standards · 2007 · 11 citations

Engineering, Materials Science, Nuclear Engineering +17