Results 101 to 110 of about 278 (148)

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
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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.
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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
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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
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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
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Russian WWER Surveillance Specimen Programs

2018
This paper describes surveillance specimen programs of Water-Water Energetic Reactor (WWER) water-cooled water-moderated reactor pressure vessels and experiences of controlling the properties of first-generation WWER-440 reactor pressure vessels, which do not have surveillance specimens.
Anna Chernobaeva, Dmitry Erak, Vyacheslav Kochkin   +2 more
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Advanced method for WWER RPV embrittlement assessment

International Journal of Pressure Vessels and Piping, 2004
Abstract The integrity assessment of reactor pressure vessels (RPV) is a main issue of NPP safe operation. Mechanical properties of the PV materials are degrading progressively under neutron irradiation reducing safety margins. To estimate the current state of embrittlement and to predict actual RPV safe life, it is necessary to develop improved ...
L Debarberis, A Kryukov, D Erak, Yu Kevorkyan, D Zhurko   +4 more
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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
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The LBB project for the new generation of WWER plants and lessons learned from the WWER 440 model 230 LBB project

Nuclear Engineering and Design, 1995
As part of the safety enhancement of WWER-type nuclear power plants (NPPs) with model 213 and 320 reactors operated or constructed in the Czech and Slovak Republics, the leak-before-break (LBB) methodology is applied to main circulating pipe and pressuriser surge lines. The typical feature of all these NPPs is the horizontal type steam generator.
J. Žd'árek, L. Pečínka, F. Kašpar
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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
openaire   +1 more source