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

Author(s):  
Peter Ebbesmeyer ◽  
Jürgen Gausemeier ◽  
Holger Krumm ◽  
Thorsten Molt ◽  
Thomas Gruß

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.

2001 ◽  
Vol 1 (3) ◽  
pp. 257-260 ◽  
Author(s):  
Peter Ebbesmeyer ◽  
Ju¨rgen Gausemeier ◽  
Holger Krumm ◽  
Thorsten Molt ◽  
Thomas Gruß

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.


Author(s):  
Xuming Wang ◽  
Cenxi Yuan ◽  
Chen Ye

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.


Author(s):  
Terry L. Schulz ◽  
Timothy S. Andreychek ◽  
Yong J. Song ◽  
Kevin F. McNamee

The AP1000 is a pressurized water reactor with passive safety features and extensive plant simplifications that provides significant and measurable improvements in safety, construction, reliability, operation, maintenance and costs. The design of the AP1000 incorporates a standard approach, which results in a plant design that can be constructed in multiple geographical regions with varying regulatory standards and expectations. The AP1000 uses proven technology, which builds on more than 2,500 reactor years of highly successful Westinghouse PWR operation. The AP1000 received Final Design Approval by the Nuclear Regulatory Commission in September 2004. The AP1000 Nuclear Power Plant uses natural recirculation of coolant to cool the core following a postulated Loss Of Coolant Accident (LOCA). Recirculation screens are provided in strategic areas of the plant to remove debris that might migrate with the water in containment and adversely affect core cooling. The approach used to avoid the potential for debris to plug the AP1000 recirculation screens is consistent with the guidance identified in Regulatory Guide 1.82 Revision 3, the Pressurized Water Reactor (PWR) Industry Guidance of NEI 04–07, and the Nuclear Regulatory Commission’s Safety Evaluation on NEI 04–07. Various contributors to screen plugging were considered, including debris that could be produced by a LOCA, resident containment debris and post accident chemical products that might be generated in the coolant pool that forms on the containment floor post-accident. The solution developed for AP1000 includes three major aspects, including the elimination of debris sources by design, features that prevent transportation of debris to the screens and the use of large advanced screen designs. Measures were taken to design out debris sources including fibers, particles and chemicals. Available industry data from walkdowns in existing plants is used to determine the characteristics and amounts of the fibrous and particulate debris that could exist in containment prior to the LOCA. Materials used in the AP1000 containment are selected to eliminate post accident chemical debris generation. Large, advanced screen designs that can tolerate significant quantities of debris have been incorporated. Testing has been performed which demonstrates that the AP1000 screens will have essentially no head loss considering the debris that could be transported to them. Testing has also been performed on an AP1000 fuel assembly that demonstrates that it will also have essentially no head loss considering the debris that could be transported to it.


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