Results 91 to 100 of about 259 (131)
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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   +4 more
openaire   +1 more source

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   +2 more
openaire   +1 more source

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
openaire   +1 more source

Radiation Stability of WWER-440 Vessel Materials

1993
The main results of a complex investigation of radiation embrittlement of WWER-440 reactor vessel (RV) materials, carried out in the former USSR are presented. The object of the investigation was surveillance specimen (SS) evaluations of RV materials. It has been found that at an irradiation temperature of 270°C neither the base metal (steel 15 Kh2MFA)
AD Amayev   +3 more
openaire   +1 more source

Radiation stability of WWER RPV cladding materials

International Journal of Pressure Vessels and Piping, 2007
Abstract A study investigating the WWER-440/213 reactor pressure vessel (RPV) cladding properties and their degradation due to neutron irradiation has been recently completed under an Hungarian National Government funded project “Evaluation of the lifetime of NPP structural materials”.
Gillemot, F.   +7 more
openaire   +2 more sources

Finite-element based vibration analysis of WWER-440 type reactors

Annals of Nuclear Energy, 1999
Abstract A finite-element model describing the mechanical vibrations of the whole WWER-440 primary circuit was established to support the early detection of mechanical component faults. A special fluid–structure module was developed to consider the reaction forces of the fluid in the downcomer upon the moving core barrel and the reactor pressure ...
Altstadt, E., Weiss, F.-P.
openaire   +3 more sources

Finite Element–Based Vibration Analysis of WWER-440 Reactors

Nuclear Technology, 1999
A finite element model describing the mechanical vibrations of the whole WWER-440 primary circuit was established to support the early detection of mechanical component faults.
Altstadt, E., Weiß, F.-P.
openaire   +1 more source

The role of chemical composition in WWER RPV irradiation embrittlement

International Journal of Nuclear Knowledge Management, 2010
The main chemical elements influencing WWER RPV steel radiation embrittlement are copper, phosphorus, nickel and manganese. Copper and phosphorus are the main influencing elements for WWER-440 RPVs. The influence of copper is implemented in the forming of nanocluster centres rounded by other elements which are the effective barriers to dislocation ...
Alexander Kryukov   +3 more
openaire   +1 more source

Lifetime Management of WWER Reactor Pressure Vessels

Aging Management and License Renewal, 2004
Reactor pressure vessels are the most important components of nuclear power plants from safety and economic point of view. Thus, special interest is given to their lifetime management that requires a precious and periodical evaluation of their conditions.
openaire   +1 more source

Surveillance Specimen Programs for WWER Type Reactors

Volume 7: Operations, Applications, and Components, 2005
Reactor pressure vessels (RPV) are components with the highest importance for the reactor safety and operation as they contain practically whole inventory of fission material but they are damaged/aged during their operation by an intensive reactor radiation.
openaire   +1 more source

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