Analysis of Relationship Between the Radiation Embrittlement Mechanisms and the Influence of Neutron Flux in Respect of WWER Reactor Pressure Vessel Materials

By Margolin B.   Yurchenko E.   Morozov A.   Pirogova N.  

Strength of Materials, Vol. 45, Iss. 4, 2013-07 ,pp. : 406-423

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Interpretation of Accelerated Irradiation Results for Materials of WWER-1000 Reactor Pressure Vessels

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Strength of Materials, Vol. 45, Iss. 4, 2013-07 ,pp. : 424-432

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Determination of stress intensity factors for semielliptical surface cracks in the WWER-1000 reactor pressure vessel from the results of solving thermoelasticity boundary value problems based on the mixed mesh-projection scheme of the finite element method

By Kharchenko V.   Kobel’skii S.   Kravchenko V.   Chirkov A.   Zvyagintseva A.  

Strength of Materials, Vol. 39, Iss. 2, 2007-03 ,pp. : 138-143

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The use of master curve method for statistical re-evaluation of surveillance test data for WWER-1000 reactor pressure vessels

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Corrosion-Mechanical Properties of Materials for Reactor Vessels

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