Integrated Surveillance Specimen Program for WWER-1000/V-320 Reactor Pressure Vessels by Brumovský, M., Brynda, J., Kytka, M., Novosad, P., Žďárek, J.

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Study of Aging Mechanisms for Structural Materials within SAFELIFE Project by Sevini, F., Debarberis, L., Taylor, N., Gerard, R., Brumovsky, M.

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Prediction of irradiation embrittlement in WWER-440 Reactor Pressure Vessel materials by Brumovsky, M., Kytka, M., Debarberis, L., Gillemot, F., Kryukov, A., Valo, M.

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Use of a Semi-Mechanistic Analytical Model to Analyze Radiation Embrittlement of Model Alloys: Cu and P Effects by Debarberis, L., Kryukov, A., Gillemot, F., Valo, M., Morozov, A., Brumovsky, M., Acosta, B., Sevini, F.

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