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IWGHTR--3: Mechanical behaviour of graphite for HTRs

Specialists meeting on mechanical behaviour of graphite for HTRs, Gif-sur-Yvette, France, 11-13 June 1979.

International Atomic Energy Agency, Vienna (Austria). International Working Group on High-Temperature Reactors., IWGHTR--3

Abstract

The specialists meeting on the mechanical behaviour of graphite for high temperarute reactors was held at the facilities of the French Atomic Energy Commission (CEA) at Gif-sur-Yvette, France on 11-13 June 1979.

During the meeting papers were presented by the participants on behalf of their countries or organizations. Each presentation was followed by an open discussion in the general area covered by the paper, and subsequently session summaries were drafted.

The technical sessions were divided into five topical sections as follows:

  1. Design Criteria
  2. Stress Analysis - Comparison with Experiments
  3. Strength Measurements
  4. Creep and Fatigue
  5. Failure Criteria

After the formal presentations were completed, a special discussion session was held on the subject of a recent report by the Franklin Institute which reviews currently used methods for structural analysis of graphite components for High Temperature Reactors (HTR). The meeting was concluded with a general panel discussion.

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Tucker, M.O. (Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs.)

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Oku, T.; Eto, M.; Arai, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)

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