Results 201 to 210 of about 1,270 (244)
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Towards a Direct Numerical Simulation of a Simplified Pressurized Thermal Shock
Flow, Turbulence and Combustion, 2018The aim of this research work is to perform high quality direct numerical simulations (DNS) of a simplified single phase pressurized thermal shock (PTS) scenario with and without buoyancy effects. In that context, the objectives of this paper are (i) to present the road towards the DNS of a PTS design without buoyancy effects and (ii) to demonstrate ...
A. Shams, E. M. J. Komen
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Pressure vessel integrity under pressurized thermal shock conditions
Nuclear Engineering and Design, 1984Abstract The currently urgent subject of pressure vessel integrity under pressurized thermal shock (PTS) conditions is discussed. A survey of events leading to PTS is made. The position of the US Nuclear Regulatory Commission on the subject is given. Finally the action taken by utilities to mitigate the effects of PTS on reactor vessels is described.
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Thermal-stress modeling of AP1000 reactor pressure vessel due to transient pressurized thermal shock
SCIENTIA SINICA Technologica, 2017Reactor pressure vessel is one of the most important components in the reactor system. In case of a loss of coolant accident, low temperature cooling water is injected into the pressurized reactor through the injection nozzle, resulting in severe pressurized thermal shock phenomenon.
ZiQi MA +5 more
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Comprehensive Modelling of Pressurized Thermal Shock With a Probabilistic Approach
Volume 3: Fluid-Structure Interaction, 2023Abstract Pressurized thermal shock (PTS) may cause a quick, catastrophic cleavage fracture in a reactor pressure vessel (RPV) of a pressurized water reactor (PWR). Low temperatures, thermal strains, and radiation embrittlement can all combine to create dangerous situations for structures, specifically thick-walled reactor pressure ...
Fabio Pasti +4 more
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Round robin analysis of pressurized thermal shock for reactor pressure vessel
Nuclear Engineering and Design, 2003A comparative assessment study is performed here for deterministic fracture mechanics analysis of a pressurized thermal shock (PTS). A round robin problem is proposed using the data available in Korea and all organizations interested in the PTS analysis are invited.
Myung Jo Jhung +3 more
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Modelling the effects of pressure thermal shock in a nuclear reactor
AIP Conference Proceedings, 2021Modelling and simulation of physical and technological processes using computational numerical methods available in today's information age represent an excellent tool for the detailed study of experimentally difficult to replicate, transient processes.
Gabriel Gálik +3 more
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Treatment of the thermal–hydraulic uncertainties in the pressurized thermal shock analysis
Nuclear Engineering and Design, 2007Abstract The pressurized thermal shock (PTS) analysis is a quantitative analysis to calculate the vessel failure probability of the embrittled reactor pressure vessel. The PTS analysis consists of three major parts, such as the probabilistic safety analysis (PSA), the thermal–hydraulic analysis (T/H), and the probabilistic fracture mechanics (PFM ...
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Pressurized thermal shock tests with model pressure vessels
1992Pressurized thermal shock experiments are performed in the Prometey Institute for the purpose of investigating the behaviour of surface flaws under pressurized water reactor overcooling accident conditions. The model pressure vessels are made of a steel 15X2MFA.
Keinänen, Heikki +8 more
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PWR annulus thermal hydraulics important to analysis of pressurized thermal shock
Nuclear Engineering and Design, 1987Abstract Analysis of plume mixing in the annulus of a pressurized water reactor (PWR) are presented. The plume mixing analysis is based on a simple two-dimensional model that accounts for the surrounding flow and confinement. A correlation for entrainment is presented and comparison with experiment is made.
Larry W. Swanson, Ivan Catton
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CFD-Tools Qualification for Thermal-Hydraulics Pressurized Thermal Shock Analysis
Journal of Pressure Vessel Technology, 2003This paper explains the numerical program concerning the E.D.F. CFD tools qualification for Safety Injection studies. Within the frame of the plant life time project, an analysis has shown that the most severe loading conditions are generated by a pressurized injection of cold water in the downcomer of a Reactor Pressure Vessel.
A. Martin, S. Bellet
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