Results 81 to 90 of about 259 (131)

Surveillance of WWER-440Č Reactor Pressure Vessels

1993
In Czechoslovakia there are six units of Water-Water Power Reactor (WWER)-440Č type reactors (pressurized water reactor [PWR] type) incorporated with pressure vessel surveillance specimens. These sets of specimens are kept for carrying out static tensile testing, impact notch toughness testing, and static fracture toughness testing, and are ...
M Brumovský, T áš Páv
exaly   +2 more sources

Evolution of the structure of the WWER-1000 reactor vessel from the prototype model to WWER-1200

Strength of Materials, 2010
We discuss the guidelines used in the design of the vessels of WWER-1000 (water-cooled water-moderated) nuclear reactors. The characteristic specific features of the structure of the reactor vessel are discussed, and the subsequent steps of improvement of its design aimed at the increase in its operating safety and designed service life up to 60 years ...
V. I. Bakaldin, V. I. Kashirin, V. V. Petrov, V. G. Fedosov   +3 more
openaire   +1 more source

Destructive analysis of the nuclide composition of spent fuel of WWER-440, WWER-1000, and RBMK-1000 reactors

Radiochemistry, 2008
The results of analysis of spent nuclear fuel (SNF) by destructive methods, carried out systematically at the Khlopin Radium Institute for over 20 years till the mid-1990s, are presented. These data constitute the experimental base for the development of nondestructive methods, correction of calculation programs, substantiation of correlation ...
T. P. Makarova, B. A. Bibichev, V. D. Domkin   +2 more
openaire   +1 more source

Neutron Dosimetry Overview for WWERs

2018
Neutron dosimetry is a mandatory part of the monitoring of irradiation conditions within the reactor pressure vessels (RPVs) of all type of reactors, including water-water energetic reactors (WWERs). The main experimental part is connected with the surveillance specimen programs because the determination of neutron fluence in each of the surveillance ...
Milan Brumovský, Milan Marek
openaire   +1 more source

Remote Dismantling of the WWER Reactors in Greifswald

Volume 3: Hazardous Waste; Engineered/Geological Barriers in Disposal Systems; L/ILW; Radioactive Waste From Research/Industries; Spent Fuel/HLW Disposal; Public Involvement; Remediation of Uranium Mining/Milling; LL/ILW; Clearance/Exemption Levels; Mgmt. of Fissile Material; HLW; Dismantling; Reversible/Irreversible Disposal; Waste Avoidance/Minimization; Decontamination; Liquid Waste; Radioactive Waste Processing; Transport of Spent Fuel/HLW; Solid HLW Confinement; QA/QC, 2001
Abstract At the Greifswald site, there are 8 units of the Russian pressurised water reactor type WWER 440. After the reunification of Germany, it was decided to decommission all units without a safe enclosure phase. Due to the high activation of the components of the reactors 1 to 4, it was necessary to use mainly remote ...
Ralf Borchardt, Jürgen Raasch
openaire   +1 more source

Assessment of the WWER-1000 reactor condition

International Journal of Pressure Vessels and Piping, 2006
The current state of the materials (steel, welds, anticorrosive cladding metal) of WWER-1000 RPVs has been examined, taking into consideration special features of their manufacture and operation for 30 years. The possibility of operating these reactors after their design service life has been estimated, allowing for the degradation of properties due to
B.T. Timofeev, G.P. Karzov
openaire   +1 more source

Application of annealing for extension of WWER vessel lives

Nuclear Engineering and Design, 1992
Abstract The safe operation of nuclear power plants (NPP) is dependent upon the assurance that the reactor pressure vessel will not fail in a brittle manner when the effects of radiation embrittlement are taken into account. The recovery of the properties of the irradiated materials is an important way of extending the operating life of a reactor ...
Vladimir Badanin, Yuri G. Dragunov, Valentin Fedorov, Igor Gorynin, Vladimir Nickolaev   +4 more
openaire   +1 more source

Progress in RI ISI Applications for WWER 440 and WWER 1000 Type Piping Systems

Volume 5: High Pressure Technology; Nondestructive Evaluation Division; Student Paper Competition, 2009
The technical publication contains a review of four risk informed inservice inspection pilot studies focused on WWER 440 and WWER 1000 type piping systems. All applications conducted in close co-operation with EPRI staff were based on modified EPRI RI ISI methodology for WWER type NPPs.
openaire   +1 more source

Probability of Rupture for WWER-1000 Main Piping

Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, 2020
Abstract A probability of rupture for WWER-1000 main piping was calculated based on the Failure Assessment Diagram (FAD), treating material properties of welds (the most likely zone for crack growing and its nucleation) and crack morphology parameters as stochastic values.
Yaroslav Dubyk, Maksym Zarazovskii, Sergii Ageiev, Vladislav Filonov   +3 more
openaire   +1 more source

Current Issues in Operated WWER Type RPVs

Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 2008
RPVs of WWER type reactors are manufactured from other type of steels (15Kh2MFA of Cr-Mo-V type for WWER-440 and 15Kh2NMFA of Ni-Cr-Mo-V type for WWER-1000) and according to other Codes and standards than PWR ones, thus some specific problems are currently more important for WWER.
Milan Brumovsky´, Milos Kytka
openaire   +1 more source