Results 71 to 80 of about 259 (131)

WWER-1300 safety systems analysis

, 2016
Leontyeva, D. A., Kakhanov, N. S., Mahmudov, F. A.   +2 more
openaire   +1 more source

Residual heat comparison for stationary campaigns of WWER-1000 and WWER-1200 reactors after preliminary storage in the spent fuel pool

Journal of Physics: Conference Series, 2018
A Piatrouski, E Rudak, T Korbut, M Kravchenko   +3 more
openaire   +1 more source

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Analysis of embrittlement of WWER-1000 RPV materials

International Journal of Pressure Vessels and Piping, 2012
Abstract Analysis of embrittlement for WWER-1000 RPV materials is performed on the basis of available and original experimental data. Contributions of thermal aging and neutron irradiation to embrittlement are considered for base and weld metals. Equations have been obtained for the shift of the critical temperature of brittleness as a function of ...
B Z Margolin
exaly   +2 more sources

WWER RPV embrittlement: start of life toughness

International Journal of Nuclear Knowledge Management, 2011
It is well known that neutron irradiation affects the properties of reactor pressure vessel material. The methodologies to assess the embrittlement of LWR (PWR, BWR and WWER types) are all based on the shift induced by irradiation of a reference transition temperature.
Marta Serrano
exaly   +2 more sources

WWER RPV Surveillance Programs

2018
Water-water energetic reactors (WWERs) are, in principle, pressurized water reactors but designed and manufactured from Russian-type materials and operated according to former Soviet/Russian rules, standards, and requirements. Their surveillance specimen programs are designed, manufactured, operated, tested, and evaluated with the same purpose but with
exaly   +2 more sources

Evaluation of WWER-440 Surveillance at Paks NPS

1989
The surveillance program of the WWER-440 type pressurized water reactors (PWRs) is somewhat different from the surveillance programs of other PWRs. In view of this, a surveillance evaluation system was developed to solve the open questions connected with the design. This system was used to evaluate the results of the first two units of Paks NPS.
F Gillemot, P Trampus, J Rittinger
exaly   +2 more sources

A historical review of WWER RPV embrittlement issues

International Journal of Nuclear Knowledge Management, 2011
The paper tries to describe the history of the radiation effects study in WWER type reactor pressure vessels – from their design, manufacturing and operation point of view. The paper shows the time evolution and also institutions that were and are included in this research and development study.
Milan Brumovsky, Vladimir Nikolaev
exaly   +2 more sources