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.

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

2000 ◽  
Author(s):  
Peter Ebbesmeyer ◽  
Jürgen Gausemeier ◽  
Holger Krumm ◽  
Thorsten Molt ◽  
Thomas Gruß
Keyword(s):  
Object Oriented ◽  
3D Models ◽  
Plant Design ◽  
Pressurized Water Reactor ◽  
Plant Structure ◽  
Pressurized Water ◽  
Web Based ◽  
Water Reactor ◽  
Engineering Information ◽  
New Type

Abstract The European Pressurized Water Reactor Project (EPR) is based on an innovative design concept for a new type of pressurized water reactor. The development of this concept will be carried out by a consortium of international partners and customers based in Germany and France. During the development of the EPR large amounts of up-to-date engineering data (i.e. CAD data, planning documentation) have to be made available to all project partners for presentation and development. This paper describes the web-based tool Virtual Web Plant (VWP), a tool to integrate 3D models from various CAD plant design tools and to display them interactively. The tool receives the data through the Internet. We describe the special advantages of an object-oriented database for the storage of the graphical data are shown. Through the application of object-oriented databases, it is possible to define various views of the logical plant structure, for example. 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.

Performances Analyses of Crud of EPR Fuel Assembly

2017 ◽  
Author(s):  
Xuming Wang ◽  
Cenxi Yuan ◽  
Chen Ye
Keyword(s):  
Risk Assessment ◽  
Fuel Assembly ◽  
Low Risk ◽  
Third Generation ◽  
Pressurized Water Reactor ◽  
Worst Case ◽  
Pressurized Water ◽  
Water Reactor ◽  
Advanced Fuel ◽  
New Type

Taishan European Pressurized Water Reactor (EPR) is a third generation advanced pressurized water reactor (PWR), which adopts the third generation advanced fuel assembly (AFA-3G-LE) from AREVA for the first time. As suggested by American Electric Power Research Institute (EPRI), an EPRI level III crud risk assessment is necessary for new type of plants. Because crud induced power offset (CIPS) and crud induced local corrosion (CILC) can lead to axial offset anomaly (AOA) and fuel cladding failure, respectively. A EPRI level III CIPS/CILC risk assessment for Taishan EPR is performed with a new framework of simulation by using sub-channel code FLICA, crud code BOA, and Monte Carlo transport code Tripoli-4. Such framework enables a self-consistent calculation, including a detailed description on neutronics contributed by boron. The validation of present work is confirmed because of the good agreement with the experienced data of EPRI. The results show that AFA-3G-LE has a good performance on crud risk assessment. Even in the worst case, the boron-10 deposition (2.6 g) and the maximum thickness of crud (59 μm) are lower than the low risk threshold, 31.33 g and 75 μm, respectively. Hence, It is expected that Taishan EPR has a very low risk on CIPS and CILC.

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.

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