Structural Materials for Innovative Nuclear Systems Workshop Proceedings Karisruhe Germany 4 6 June 2007 1st Edition by OECD Organisation for Economic Co operation and Development ISBN 9264048065 9789264048065 by Bernan 9264048065, 9789264048072 instant download after payment.

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ISBN 10: 9264048065 
ISBN 13: 9789264048065
Author: OECD Organisation for Economic Co operation and Development

Structural Materials for Innovative Nuclear Systems Workshop Proceedings Karisruhe Germany 4 6 June 2007 1st Table of contents:

Session I: Keynote Lectures

• (This section would feature overarching presentations setting the stage for the workshop, perhaps covering the vision for Generation IV reactors and the critical role of materials.)
  • Example: Overview of Materials Challenges for Generation IV Systems
  • Example: Advanced Modeling for Nuclear Materials Performance

Session II: Gas-Cooled Systems (e.g., VHTR, GFR)

• (Papers focusing on materials issues for Very High Temperature Reactors and Gas-cooled Fast Reactors.)
  • Example: High-Temperature Alloys for VHTR Core Components
  • Example: Irradiation Effects on Graphite and SiC Composites
  • Example: Corrosion Behavior of Alloys in High-Temperature Helium

Session III: Liquid-Metal-Cooled Systems (e.g., SFR, LFR)

• (Papers on materials for Sodium-cooled Fast Reactors and Lead-cooled Fast Reactors.)
  • Example: Ferritic/Martensitic Steels for SFR Applications
  • Example: Compatibility of Materials with Liquid Lead-Bismuth Eutectic
  • Example: Cladding Materials for Fast Reactor Fuels

Session IV: Fusion, High-Power Accelerator Targets, and Other Fission Reactor Systems

• (A broader session covering materials for fusion reactors, spallation neutron sources, and potentially advanced light water reactors.)
  • Example: Candidate Materials for Fusion Reactor First Walls
  • Example: Radiation Damage in High-Power Target Materials
  • Example: Accident-Tolerant Fuels and Claddings

Session V: Fundamental Research and Cross-Cutting Issues

• (Papers on underlying scientific principles and methodologies applicable across various reactor types.)
  • Example: Multi-Scale Modeling of Radiation Damage
  • Example: Advanced Characterization Techniques for Irradiated Materials
  • Example: Creep and Fatigue Behavior of Advanced Alloys
  • Example: Environmental Degradation Mechanisms

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Tags: OECD Organisation for Economic Co operation and Development, Materials, Innovative