Results 101 to 110 of about 674,656 (134)

Application of Master Curve Approach to WWER-1000 RPV Materials

Fatigue, Fracture and Damage Analysis, Volume 1, 2002
Part of the IRLA (International Residual Life Assessment) project was concentrated on a detailed analysis of existing and available fracture toughness data of WWER-1000 (Water-Water-Energetical-Reactor) reactor pressure vessel materials – steel 15Kh2NMFA (Ni-Cr-Mo-V) type and its welding metals.
Milan Brumovsky, Antonio Ballesteros
openaire   +1 more source

WWER-1000 shutdown probabilistic risk assessment: An introductory insight

Annals of Nuclear Energy, 2008
Abstract The probabilistic risk assessment has become an essential part of every plant’s safety/risk analysis. In the past, regulations and safety assessments of nuclear power plants were traditionally concentrated on full power operation. However, because of the events that might potentially occur during low power and shutdown modes, the assessment ...
openaire   +1 more source

Analysis of WWER 1000 Fuel Cladding Failure

2022
Maksym Maksymov, Svitlana Alyokhina, Oleksandr Brunetkin   +2 more
openaire   +1 more source

AUTONOMOUS THERMOSIPHON SYSTEM FOR WWER 1000 COOLDOWN

Heat Pipe Science and Technology, An International Journal, 2011
Igor I. Sviridenko, Dmitriy V. Shevielov
openaire   +1 more source

DOSIMETRY EXPERIMENTS ON WWER-1000 MOCK-UP WITH MODEL OF IRRADIATION RIG OF NOVO VORONEZH UNIT 5 WWER-1000

Reactor Dosimetry in the 21st Century, 2003
S.M. Zaritsky, E.B. Brodkin, A.L. Egorov, D.Yu. Erak, V.I. Vikhrov, N.V. Markina, D.K. Ryazanov, V.V. Lichadeev, A.I. Tellin, S.S. Lomakin, E.I. Grigoriev, B. Ošmera, S. Pošta, B. Jansky, E. Novák, F. Cvachovec, P. Tiller   +16 more
openaire   +1 more source

An improved method for automated control of the WWER-1000 power maneuvering

2018
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Huiyu Zhou, Pelykh, S.N., Foshch, T.V., Maksymova, O.B.   +3 more
openaire   +1 more source

Strength analysis of WWER-1000 reactor fuel assembly

Politechnical student journal, 2021
openaire   +1 more source

An autonomous system of a spent fuel pool cooling in WWER-1000

2018
The issue of WWER-1000 spent fuel pool cooling in total blackout conditions is evaluated. A model of a spent fuel pool for MELCOR computer code is developed. Basic information about a spent fuel pool construction is shown. Basic data for a spent fuel pool cooling system calculations are given.
openaire   +1 more source

Assessment of radioactive contamination in primary circuit of WWER-440 type reactors by computer code OSCAR for the decommissioning case

Progress in Nuclear Energy, 2019
Frédéric Dacquait, Jean-Baptiste GENIN, Arturas Plukis   +2 more
exaly  

Determination of the maximum speed of WWER-1000 nuclear reactor control rods

Annals of Nuclear Energy, 2016
Farrokh Khoshahval
exaly