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, 2004Abstract 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
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Russian WWER Surveillance Specimen Programs
2018This 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
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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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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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Radiation Stability of WWER-440 Vessel Materials
1993The 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
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Radiation stability of WWER RPV cladding materials
International Journal of Pressure Vessels and Piping, 2007Abstract 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
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Finite-element based vibration analysis of WWER-440 type reactors
Annals of Nuclear Energy, 1999Abstract 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.
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Finite Element–Based Vibration Analysis of WWER-440 Reactors
Nuclear Technology, 1999A 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.
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The role of chemical composition in WWER RPV irradiation embrittlement
International Journal of Nuclear Knowledge Management, 2010The 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
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Lifetime Management of WWER Reactor Pressure Vessels
Aging Management and License Renewal, 2004Reactor 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.
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Surveillance Specimen Programs for WWER Type Reactors
Volume 7: Operations, Applications, and Components, 2005Reactor 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.
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