Search Results1-10 of  10

  • OSAKABE Kazuya ID: 9000001241514

    Fuji Research Institute Corporation (2004 from CiNii)

    Articles in CiNii:1

    • Plasto-viscoelastic simulation of the crustal deformation (2004)
  • OSAKABE Kazuya ID: 9000303988219

    Mizuho Information (2013 from CiNii)

    Articles in CiNii:1

    • 2712 SCC and Fatigue Crack Propagation Analyses on Deep Semi-Elliptical Flaws under Residual Stress Field (2013)
  • OSAKABE Kazuya ID: 9000303989208

    Mizuho Information & Research Institute (MHIR) (2014 from CiNii)

    Articles in CiNii:6

    • Development of Probabilistic Fracture Mechanics Analysis Code PASCAL ver. 2 for Reactor Pressure Vessel (2007)
    • Probabilistic Evaluation of Current Structural Integrity Assessment Method for Reactor Pressure Vessel Using PASCAL ver. 2 (2007)
    • OS1410 Evaluation of Through-wall Cracking Frequency of Reactor Pressure Vessel under Pressurized Thermal Shock events (2013)
  • Osakabe Kazuya ID: 9000258495264

    Tokyo Institute of Technology (2002 from CiNii)

    Articles in CiNii:1

    • Stress update algorithm for rate-independent Sekiguchi-Ohta model (2002)
  • Osakabe Kazuya ID: 9000258495272

    Tokyo Institute of Technology (2002 from CiNii)

    Articles in CiNii:1

    • Consistent tangential moduli for rate-independent Sekiguchi-Ohta model (2002)
  • Osakabe Kazuya ID: 9000258500134

    Tokyo Institute of Technology (2003 from CiNii)

    Articles in CiNii:1

    • Elasto-plastic Constitutive Model Considering Decay of Structure and Iso/aniso-tropization (2003)
  • Osakabe Kazuya ID: 9000392075698

    Japan Atomic Energy Agency (2006 from CiNii)

    Articles in CiNii:1

    • Development of RPV Integrity Analysis Code PASCAL Ver.2 Based on Probabilistic Fracture Mechanics Methodology (2006)
  • Osakabe Kazuya ID: 9000392106799

    Japan Atomic Energy Agency (2007 from CiNii)

    Articles in CiNii:1

    • Study on Stress Intensity Factor Evaluation Method for the Probabilistic Fracture Mechanics Analysis of Reactor Pressure Vessel (2007)
  • Osakabe Kazuya ID: 9000392130120

    Mizuho Infromation & Research Institute (2010 from CiNii)

    Articles in CiNii:1

    • Study on Safety Margin Assessment of Reactor Structural Components based on Failure Probabilities (2010)
  • osakabe kazuya ID: 9000392098225

    Mizuho Information & Research Institute,Inc. (2009 from CiNii)

    Articles in CiNii:1

    • Strength Evaluation of Crust Formed during Molten Core-Concrete Interaction (2009)
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