Current status of the small punch test standardization within the ASTM von Kopriva, R., Brumovsky, M., Petelova, P.

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Irradiation embrittlement characterization of the EUROFER 97 material von Kytka, M., Brumovsky, M., Falcnik, M.

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Common comparison of the irradiation embrittlement of WWER/PWR reactor pressure vessel steels von Kryukov, A., Nanstad, R.K., Brumovsky, M.

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Analysis of a link of embrittlement mechanisms and neutron flux effect as applied to reactor pressure vessel materials of WWER von Margolin, B.Z., Yurchenko, E.V., Morozov, A.M., Pirogova, N.E., Brumovsky, M.

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Monitoring radiation embrittlement during life extension periods von Ballesteros, A., Altstadt, E., Gillemot, F., Hein, H., Wagemans, J., Rouden, J., Barthelmes, J., Wilford, K., Serrano, M., Brumovsky, M., Chaouadi, R., Ortner, S.

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Structural MATerias research on parameters influencing the material properties of RPV steels for safe long-term operation of PWR NPPs von Kolluri, M., Martin, O., Naziris, F., D'Agata, E., Gillemot, F., Brumovsky, M., Ulbricht, A., Autio, J-M., Shugailo, O., Horvath, A.

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Role of nickel in a semi-mechanistic analytical model for radiation embrittlement of model alloys von Debarberis, L., Acosta, B., Sevini, F., Kryukov, A., Gillemot, F., Valo, M., Nikolaev, A., Brumovsky, M.

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Effect of irradiation temperature in PWR RPV materials and its inclusion in semi-mechanistic model von Debarberis, L., Acosta, B., Zeman, A., Sevini, F., Ballesteros, A., Kryukov, A., Gillemot, F., Brumovsky, M.

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Analysis of WWER-440 and PWR RPV welds surveillance data to compare irradiation damage evolution von Debarberis, L., Acosta, B., Zeman, A., Sevini, F., Ballesteros, A., Kryukov, A., Gillemot, F., Brumovsky, M.

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Cladding in RPV Integrity and Lifetime Evaluation von Brumovsky, M., Kytka, M., Kopriva, R.

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WWER-1000 base metal reference steel and its characterisation von Acosta, Beatriz, Debarberis, Luigi, Pirfo, Soraia, Sevini, F., Kryukov, A., Chernobaeva, A., Gillemot, F., Brumovsky, M.

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Assessment by comparison and experimental verification of VVER reactor pressure vessel integrity von Brumovsky, M.

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Study of aging mechanisms for structural materials within SAFELIFE project von SEVINI, F, DEBARBERIS, L, TAYLOR, N, GERARD, R, BRUMOVSKY, M

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

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Check of Master Curve application to embrittled RPVs of WWER type reactors von Brumovsky, M

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5 - Embrittlement of reactor pressure vessels (RPVs) in WWER-type reactors von Brumovsky, M.

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3 - WWER-type reactor pressure vessel (RPV) materials and fabrication von Brumovsky, M.

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Measurement of fracture toughness transition behaviour of Cr–Ni–Mo–V pressure vessel steel using pre-cracked Charpy specimens von Holzmann, M, Dlouhý, I, Brumovský, M

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The Euratom 5th Framework Programme Project FRAME (fracture mechanics based embrittlement); description of the project and first results von Valo, Matti, Wallin, Kim, Lucon, Enrico, Kytka, Milos, Brumovsky, Milan, Acosta, Beatriz, Debarberis, Luigi, Kohopää, Jyrki, Gillemot, Ferenc, Horvath, Marta

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WWER-Type Reactor Pressure Vessel (RPV) Materials and Fabrication von Soneda Naoki

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