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The design of components subjected to thermal fatigue is one of the most challenging tasks for the experimental thermonuclear fusion reactor project. In this paper the applicability of the present existing nuclear standard codes (ASME and RCC-MR) is discussed. Problems of numerical modelling and the design of technological components are also considered.

Additional information

Authors: MEROLA M, JRC Ispra (IT)
Bibliographic Reference: Paper presented: 12th International Conference on Structural Mechanics in Reactor Safety, Stuttgart (DE), August 15-20, 1993
Availability: Available from (1) as Paper EN 37625 ORA
Record Number: 199311018 / Last updated on: 1994-11-29
Original language: en
Available languages: en
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