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Abstract

Physical and thermal/mechanical interaction with plasma is considered to be the most limiting phenomenon for the first wall lifetime of the next generation tokamak fusion reactors. This paper describes the thermal fatigue test programme on NET/ITER FW components. The lifetime predictions performed according to ASME and RCC-MR codes are discussed on the basis of the numerical evaluation and of the experimental results.

Additional information

Authors: MATERA R, JRC Ispra (IT);BIGGIO M, JRC Ispra (IT);RENDA V, JRC Ispra (IT);MEROLA M, Politecnico di Milano (IT);CICCHETTI E, Politecnico di Milano (IT);ETO M, Japan Atomic Energy Research Institute, Tokai-Mura (JP)
Bibliographic Reference: Paper presented: 4th International Conference on Fusion Reactor Materials, Kyoto (JP), Dec. 4-8, 1989
Availability: Available from (1) as Paper EN 35067 ORA
Record Number: 199111245 / Last updated on: 1994-12-02
Category: PUBLICATION
Original language: en
Available languages: en