Results 211 to 220 of about 3,020,549 (269)

Probabilistic Pressurized Thermal Shocks Analyses for a Reactor Pressure Vessel

open access: yesJournal 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
openaire   +6 more sources

PRESSURE VESSEL CALCULATIONS FOR VVER-440 REACTORS

Reactor Dosimetry in the 21st Century, 2003
For the determination of the fast neutron load of the reactor pressure vessel a mixed calculational procedure was developed. The procedure was applied to the Unit II of Paks NPP, Hungary. The neutron source on the outer surfaces of the reactor was determined by a core design code, and the neutron transport calculations outside the core were performed ...
G, Hordósy   +6 more
openaire   +2 more sources

Thermo-mechanical Transient Analysis of Reactor Pressure Vessel [PDF]

open access: yesProcedia Engineering, 2014
To demonstrate the structural integrity of a reactor pressure vessel, a detailed stress analysis is required to be carried out accounting for the transients during various operating conditions of the reactor.
Balasubramanian, A.K.   +4 more
exaly   +2 more sources

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   +5 more
openaire   +1 more source

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   +2 more
openaire   +1 more source

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
openaire   +1 more source

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.
openaire   +1 more source

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   +2 more
openaire   +1 more source

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