Results 111 to 120 of about 8,242 (166)

Probabilistic Pressurized Thermal Shocks Analyses for a Reactor Pressure Vessel

Journal of Pressure Vessel Technology, 2014
Both deterministic and probabilistic methods are used to assess the integrity of a reactor pressure vessel (RPV) subjected to pressurized thermal shocks (PTSs). The FAVOR code is applied to calculate the probabilities for crack initiation and failure of the RPV subjected to two transients, by considering crack distributions based on cracks observed in ...
Qian, Guian, Niffenegger, Markus
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Embrittlement of nuclear reactor pressure vessels

JOM, 2001
Neutron irradiation embrittlement could limit the service life of some of the reactor-pressure vessels in existing commercial nuclear-power plants. Improved understanding the of the underlying causes of embrittlement has provided regulators and power-plant operators better estimates of vessel-operating margins.
G. R. Odette, G. E. Lucas
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A reliability assessment of reactor pressure vessels

International Journal of Pressure Vessels and Piping, 1994
Abstract A theoretical investigation is presented on the reliability assessment of nuclear reactor pressure vessels. In the analysis, a Poisson-type random walk model is assumed to represent the randomly occurred transients, which have randomly distributed stresses.
Tsai, Chwan-Huai, Wu, Wen-Fang, Shin, Chow-Ching   +2 more
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Dismantling of the BR3 Reactor Pressure Vessel

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 The BR3 PWR is a small nuclear power plant (thermal power 40.9 MWth, net electrical power output 10.5 MWe), designed in the late fifties and started in 1962. It was definitely shut down in 1987. In 1989 the BR3 was selected by the European Union as pilot decommissioning project in the framework of its RTD ...
M. Klein, Y. Demeulemeester, V. Massaut, H. Davain, J.-M. Brossard, J. Dadoumont   +5 more
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Annealing of nuclear reactor pressure vessels

Nuclear Engineering and Design, 1998
The neutron embrittlement that occurs in the beltline of reactor pressure vessels (RPV) can be managed by various techniques such as fuel management, but only thermal annealing can reverse the effects and result in a restoration of RPV beltline material toughness. The US Nuclear Regulatory Commission has recently revised the Code of Federal Regulations
M.G Vassilaros, M.E Mayfield, K.R Wichman   +2 more
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Stainless steel reactor pressure vessels

Nuclear Engineering and Design, 1970
Abstract The properties of stainless steels preferred for nuclear reactor pressure vessel construction, the austenitic-chromium-nickel types, are reviewed along with other bases for this nuclear application. The engineering criteria which establish the limits for design and operation, the various aspects of vessel fabrication and the implications of ...
P.J. Karnoski, W.J. Fretague, Uldis Potapovs, L.E. Steele   +3 more
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Reactor pressure vessel design and practice

Progress in Nuclear Energy, 1982
Abstract This paper attempts to review the state of the art of methods of analysis and design of the concrete reactor pressure vessels and their components. Existing vessels have been examined for elastic, inelastic and cracking conditions. The results obtained from the analyses given in the appendices are well collaborated with those available from ...
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Lift of Shippingport Reactor Pressure Vessel

Journal of Construction Engineering and Management, 1990
The Shippingport Atomic Power Station in western Pennsylvania is the first nuclear electric generating station to be decommissioned with the goal of restoring the site to a radiologically clean con...
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Concrete Reactor Pressure Vessels

2010
This chapter attempts to review the state of the art of methods of analysis and design of the concrete reactor pressure vessels and their components. Existing vessels have been examined for elastic, inelastic and cracking conditions.
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Reactor Pressure Vessel Modification Approaches

Volume 6: Materials and Fabrication, 2005
Stress corrosion cracking of Alloy 600 has lead to the modification and replacement of many nuclear power plant components. Among these components are the Bottom Mounted Nozzles (BMN) of the Reactor Pressure Vessel (RPV). Modifications of these components have been performed on an emergent basis.
Ronald J. Payne, Stephen Levesque
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