A Modified Borresen Coarse-Mesh Computation for a Three-Dimensional Pressurized Water Reactor Benchmark Problem

1983 ◽  
Vol 61 (1) ◽  
pp. 49-54 ◽  
Author(s):  
Chang Hyo Kim ◽  
Samuel H. Levine
Keyword(s):  
Three Dimensional ◽  
Coarse Mesh ◽  
Benchmark Problem ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor

Massively Parallelized Simulation of Deflagration-to-Detonation Transition in a Konvoi-Type Pressurized Water Reactor

2016 ◽  
Author(s):  
Josef Hasslberger ◽  
Peter Katzy ◽  
Thomas Sattelmayer ◽  
Lorenz R. Boeck
Keyword(s):  
Large Scale ◽  
Initial Conditions ◽  
Combustion Process ◽  
Three Dimensional ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Flow Solver ◽  
Water Reactor ◽  
Highly Sensitive ◽  
Transition Criteria

For the purpose of nuclear safety analysis, a reactive flow solver has been developed to determine the hazard potential of large-scale hydrogen explosions. Without using empirical transition criteria, the whole combustion process (including DDT) is computed within a single solver framework. In this paper, we present massively parallelized three-dimensional explosion simulations in a full-scale pressurized water reactor of the Konvoi type. Several generic DDT scenarios in globally lean hydrogen-air mixtures are examined to assess the importance of different input parameters. It is demonstrated that the explosion process is highly sensitive to mixture composition, ignition location and thermodynamic initial conditions. Pressure loads on the confining structure show a profoundly dynamic behavior depending on the position in the containment.

Comparison of Pressure-Temperature Limits for a Pressurized Water Reactor Pressure Vessel Considering Beltline and Extended Beltline Regions

2018 ◽  
Author(s):  
Hsoung-Wei Chou ◽  
Yu-Yu Shen ◽  
Chin-Cheng Huang
Keyword(s):  
Pressure Vessel ◽  
Structural Integrity ◽  
Three Dimensional ◽  
Pressure Vessels ◽  
Reference Temperature ◽  
Regulatory Body ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Reactor Pressure

To ensure the structural integrity of the embrittled reactor pressure vessels (RPVs) during startup or shutdown operation, the pressure-temperature (P-T) limits are mainly determined by the fracture toughness of beltline region material with the highest level of neutron embrittlement. However, other vessel parts such as nozzles with structural discontinuities may affect the limits due to the higher stress concentration, even though the neutron embrittlement is insignificant. Therefore, not only beltline material with the highest reference temperature, but also other components with structural discontinuities have to be considered for the development of P-T limits of RPV. In the paper, the pressure-temperature operational limits of a Taiwan domestic pressurized water reactor (PWR) pressure vessel considering beltline and extended beltline regions are established per the procedure of ASME Code Section XI-Appendix G. The three-dimensional finite element models of PWR inlet and outlet nozzles above the beltline region are also built to analyze the pressure and thermal stress distributions for P-T limits calculation. The analysis results indicate that the cool-down P-T limit of the domestic PWR vessel is still dominated by the beltline region, but the heat-up limit is partially controlled by the extended beltline region. On the other hand, the relations of reference temperature between nozzles and beltline region on the P-T limits are also discussed. Present work could be a reference for the regulatory body and is also helpful for safe operation of PWRs in Taiwan.

Virtual Web Plant: An Internet-Based Plant Engineering Information System

2001 ◽  
Vol 1 (3) ◽  
pp. 257-260 ◽  
Author(s):  
Peter Ebbesmeyer ◽  
Ju¨rgen Gausemeier ◽  
Holger Krumm ◽  
Thorsten Molt ◽  
Thomas Gruß
Keyword(s):  
Three Dimensional ◽  
Plant Design ◽  
Pressurized Water Reactor ◽  
Plant Structure ◽  
Pressurized Water ◽  
Web Based ◽  
Water Reactor ◽  
Engineering Information ◽  
New Type ◽  
Three Dimensional Models

During the development of the European Pressurized Water Reactor Project (EPR)—an innovative design concept for a new type of pressurized water reactor—large amounts of up-to-date engineering data (i.e., CAD data, planning documentation) have to be made available to all international project partners for presentation and development. This paper describes the web-based tool Virtual Web Plant (VWP), a tool to integrate three-dimensional models from various CAD plant design tools and to display them interactively. The user is hereby able to navigate easily through both the plant structure and the project documentation. The work presented in this paper is part of a Virtual Reality Research Project of the Heinz Nixdorf Institute and the Siemens AG KWU.

CFD Simulation of Fission Gas Release Under Fuel Defects Condition in Pressurized Water Reactor

2018 ◽  
Author(s):  
Bing Dong ◽  
Leihao Li ◽  
Chenyue Li ◽  
Junlian Yin ◽  
Dezhong Wang
Keyword(s):  
Cfd Simulation ◽  
Three Dimensional ◽  
Pressurized Water Reactor ◽  
Fuel Cladding ◽  
Two Phase ◽  
Release Process ◽  
Pressurized Water ◽  
Water Reactor ◽  
Fission Gas ◽  
Failure Monitoring

During normal pressurized water reactor (PWR) operation, the fuel cladding is inevitably defective. It is important to develop a model to evaluate the fission gas (FG) release from the fuel-cladding gap into the coolant, which benefits the fuel failure monitoring and improves the reactor safety. The objective of this paper is to give an overview of three-dimensional two-phase transient CFD simulation based on the Volume of Fluid (VOF) method to evaluate the fission gas migrating inside the gap and escaping through the defects. The topics of this paper include the behavior and release rate of FG in the fuel-cladding gap when the fuel cladding is defective. An analysis is presented on the suitability of the CFD simulation and it is shown that three-dimensional two-phase transient CFD simulation can be utilized in evaluating the FG release process. The results show that water enters the gap immediately after an abrupt cladding defect. The entering water flashes and causes pressure pulsation, which induces the transient FG release.

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