Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor
Nuclear Engineering and Design（2022）
Abstract
•Extension of the TRANSURANUS fuel performance code to the MYRRHA pin cladding material.•Creep and void swelling modelling of DIN1.4970.•Application of TRANSURANUS to the fuel and cladding performance analysis of MYRRHA.•Simulation of MYRRHA normal operating conditions and identification of worst-case scenarios.•Assessment of the code predictions adopting conservative design limits.
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Key words
Generation IV,MYRRHA reactor,Cladding creep and swelling,Fuel performance code,TRANSURANUS
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