Community Research and Development Information Service - CORDIS

Abstract

When considering the resistance of first wall materials to the severe thermal loading experienced in a nuclear fusion reactor, it is difficult to relate the results of disc or plate specimen tests to component behaviour. A component testing technique has been developed to provide specific data under conditions closely simulating those in service. Particular emphasis is placed on a rapid heating cycle followed by slower cooling. The application of a dc potential drop method to cracks growing from both the inner and outer surfaces of thick walled tubular test pieces can provide continuous monitoring of crack growth. The material studied is a type 316L stainless steel. Small differences in crack growth rates are found and related to defect geometries and the defect tip stresses calculated using finite element methods.

Additional information

Authors: KERR D C, JRC Petten (NL);HURST R C, JRC Petten (NL);ANDRITSOS F, JRC Ispra (IT)
Bibliographic Reference: Paper presented: 11th Conference on Structural Mechanics in Reactor Technology, Tokyo (JP), Aug. 18-23, 1991
Availability: Available from (1) as Paper EN 36138 ORA
Record Number: 199110769 / Last updated on: 1994-12-02
Category: PUBLICATION
Original language: en
Available languages: en