Thermal fatigue of a brazed fusion reactor first wall componentFunded under: JRC-FUSAFE 4C
The choice of the structural material for the first wall of ITER/NET is orientated towards an austenitic stainless steel such as AISI 316 L. Unfortunately, this has unfavourable physical properties under thermal stresses. The expected high heat loads and large number of operating cycles result in severe thermal fatigue. The aim of the thermal fatigue testing programme at JRC Ispra is to improve confidence in the prediction of the lifetime, to compare the thermo-mechanical performance of different first wall designs and to develop test procedures and design tools for larger prototypes. This paper describes the specially built thermal fatigue test facility and gives the numerical and experimental results of a brazed first wall component under thermal fatigue cycling.
Bibliographic Reference: Paper presented: 11th International Conference on Structural Mechanics in Reactor Technology SMIRT 11, Tokyo (JP), August 18-23, 1991
Availability: Available from (1) as Paper EN 35995 ORA
Record Number: 199110432 / Last updated on: 1994-12-02
Original language: en
Available languages: en