Mechanism of Change In VVER-440, -1000 Vessel Material Properties in Irradiation–Recovery Annealing–Irradiation Cycle

Assessment of segregation kinetics in water-moderated reactors pressure vessel steels under long-term operation

(2016) E.A. Kuleshova et al.   JOURNAL OF NUCLEAR MATERIALS

Current understanding of radiation-induced degradation in light water reactor structural materials

(2013) Koji Fukuya   JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY

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

(2013) D. Yu. Erak et al.   STRENGTH OF MATERIALS

A physically-based correlation of irradiation-induced transition temperature shifts for RPV steels

(2012) E.D. Eason et al.   JOURNAL OF NUCLEAR MATERIALS

Analysis of embrittlement of WWER-1000 RPV materials

(2011) B.Z. Margolin et al.   INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING

Irradiation temperature, flux and spectrum effects

(2011) A. Ballesteros et al.   PROGRESS IN NUCLEAR ENERGY

A new approach to description of in-service embrittlement of WWER-1000 reactor pressure vessel materials

(2010) B. Z. Margolin et al.   STRENGTH OF MATERIALS