Community Research and Development Information Service - CORDIS


The applicability of the presently existing nuclear standard codes (ASME and RCC-MR) in the thermal fatigue design of nuclear components is discussed with particular attention to the first wall of a fusion reactor machine. The possible extension of the results of the mechanical and thermomechanical fatigue tests, the sensitivity of the different numerical models in the calculation of the stress and strain history as well as the influence of the manufacturing technology on the thermal fatigue lifetime are tackled.

Additional information

Authors: MEROLA M, JRC Ispra (IT)
Bibliographic Reference: Article: Nuclear Engineering and Design, Vol. 158 (1995), pp. 351-361
Record Number: 199610017 / Last updated on: 1996-02-16
Original language: en
Available languages: en
Follow us on: RSS Facebook Twitter YouTube Managed by the EU Publications Office Top