Guidelines for Prediction of Irradiation Embrittlement of Operating WWER-440 Reactor Pressure Vessels
Guidelines for Prediction of Irradiation Embrittlement of Operating WWER-440 Reactor Pressure VesselsInternational Atomic Energy Agency
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Guidelines for Prediction of Irradiation Embrittlement of Operating WWER-440 Reactor Pressure Vessels

Guidelines for Prediction of Irradiation Embrittlement of Operating WWER-440 Reactor Pressure Vessels Report Prepared Within the Framework of the Coordinated Research Project

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The IAEA International Database on RPV Materials (IDRPVM) is used for prediction and analysis of radiation embrittlement of WWER-440 reactor pressure vessel (RPV) materials. These guidelines will be used for assessment of irradiation embrittlement of RPV ferritic materials as a result of degradation during operation. Two approaches, i.e. transition temperatures based on Charpy impact notch toughness as well as those based on static fracture toughness tests, are used to develop the prediction formulas for radiation embrittlement of RPVs of WWER-440 nuclear power plants.