The International Atomic Energy Agency convened, in the framework of its Fusion Technology and Engineering Programme, the 4th Technical Committee and Workshop on Fusion Reactor Design and Technology at Yalta, USSR, from 26 May – 6 June 1986. This report contains all summaries of sessions that were organized during the workshop. The papers presented at the meeting are being published by the Agency in its Proceedings Series.

https://iopscience.iop.org/article/10.1088/0029-5515/26/10/011/pdf

Fusion Reactor Design IV (Report on the 4th IAEA Technical Committee Meeting and Workshop, Yalta, USSR, 26 May – 6 June 1986)

Analysis and experiments on lifetime predictions of the first wall and divertor plate of fusion reactors have been performed. The analysis is based on both a one-dimensional plate model and a two-dimensional elastic-plastic finite element method. The experiments consist of mechanical fatigue tests, thermal fatigue tests, and tests of vaporized loss of materials. From these results, discussions of lifetime prediction procedures for fusion reactor components are made.

Analysis and Experiments on Lifetime Predictions for First Wall and Divertor Plate Structures in JAERI

Technical considerations on tritium breeding blanket systems for a fusion power reactor

Recent design studies of tokamak power reactor and related activities conducted in JAERI are presented. A design study of the SPTR (Swimming-Pool Type Reactor) concept was carried out in FY81 and FY82. The reactor design studies in the last two years focus on nuclear components, heat transport and energy conversion systems. In parallel of design studies, tokamak systems analysis code is under development to evaluate reactor performances, cost and net energy balance.

M. Nishikawa

Papers

Design studies of Tokamak power reactor in JAERI