Normative issues in thermal fatigue design of nuclear components Original Research Article

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 thermo-mechanical 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.