Download or read book An Exploratory Analysis of Thermal hydraulic Conditions Leading to Severe Accidents for the New Production Heavy Water Reactor written by and published by . This book was released on 1992 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: This study, sponsored by the New Production Reactor (NPR) Program through the Los Alamos NPR Safety Project Office, is part of the body of severe-accident review information being developed to support the safety review of the New Production Heavy-Water Reactor (NP-HWR). The NP-HWR safety study of severe beyond-design-basis events concerns two issues related to in-vessel, sudden-energy sources: wet-core recriticality and molten-fuel-and-coolant interaction (MFCI). The configuration that will lead to recriticality and MFCI is determined by the mode and coherency of the fuel-target disruption and water contact during the accident progression. The mode and coherency are, in turn, governed by the thermal-hydraulic conditions in the assembly channel and the fuel heatup rate after the assembly channels have dried out. The results of the analysis, presented for the transients out to the time of incipient fuel melt, describe the dominant features of the transients for the two severe events. The conclusions summarize what we have learned about the controlling mechanisms and important parameters for the conditions leading up to fuel melt, identify important safety review information that may be relevant to the final design, and suggest actions needed to conduct an adequate safety review of relevant aspects of the NP-HWR.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1994 with total page 464 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reports of the Technical Assessment Task Force Chemistry Thermal hydraulics Core damage WASH 1400 reactor safety study Alternative event sequences written by United States. President's Commission on the Accident at Three Mile Island. Technical Assessment Task Force and published by . This book was released on 1979 with total page 240 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Thermal hydraulic Analysis of Severe Accident Progress in Pressurized Light Water Reactor According to Its Scale written by Katarzyna Skolik and published by . This book was released on 2021 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Analysis of Severe Accidents in Pressurized Heavy water Reactors written by International Atomic Energy Agency and published by . This book was released on 2008 with total page 139 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report instructs the reader on how to perform deterministic analysis of severe accidents in pressurized heavy water reactors (PHWRs) by means of available computer codes. The analysis of accident phenomena should assist in the development of practicable preventive or mitigatory measures. In addition to providing a framework for data collection and analysis relevant to both the in- and ex-vessel phases of severe accidents, the publication also provides guidance for severe accident management.
Download or read book Proceedings of Nuclear Thermal Hydraulics written by American Nuclear Society. Thermal Hydraulics Division. Meeting and published by . This book was released on 1990 with total page 828 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Government Reports Announcements Index written by and published by . This book was released on 1993 with total page 658 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Thermal Hydraulic Analysis of a Pressurized Water Reactor During a Total Loss of AC Power Accident written by Farid Bamdad Haghighi and published by . This book was released on 1984 with total page 492 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Comparison of Heavy Water Reactor Thermalhydraulic Code Predictions with Small Break LOCA Experimental Data written by International Atomic Energy Agency and published by . This book was released on 2012 with total page 243 pages. Available in PDF, EPUB and Kindle. Book excerpt: Intercomparison and Validation of Computer Codes for Thermalhydraulics Safety Analyses is an International Atomic Energy Agency (IAEA) activity designed to facilitate international cooperative research and promote information exchange on computer codes for thermalhydraulic safety analyses. The objective is to enhance the safety analysis capabilities of the participants and the effective use of their resources through this international cooperation. This report provides a comparison of the results obtained from eight participating organisations from six countries, utilizing four different computer codes. General conclusions are reached and recommendations made
Download or read book Government Reports Annual Index written by and published by . This book was released on 1993 with total page 1834 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Ex vessel Severe Accident Review for the Heavy Water New Production Reactor written by Kenneth D. Bergeron and published by . This book was released on 1993 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Thermal hydraulics of a Boiling Water Nuclear Reactor written by Richard T. Lahey and published by . This book was released on 1993 with total page 658 pages. Available in PDF, EPUB and Kindle. Book excerpt: This edition of the classic monograph gives a comprehensive overview of the thermal-hydraulic technology underlying the design, operation, and safety assessment of boiling water reactors. In addition, new material on pressure suppression containment technology is presented.
Download or read book Metal water Reactions written by Leo F. Epstein and published by . This book was released on 1960 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Intercomparison and Validation of Computer Codes for Thermalhydraulic Safety Analysis of Heavy Water Reactors written by International Atomic Energy Agency and published by . This book was released on 2004 with total page 140 pages. Available in PDF, EPUB and Kindle. Book excerpt: Intercomparison and validation of computer codes used in different countries for thermal hydraulics safety analysis of heavy water reactors (HWRs) enhances the confidence in the predictions made by these codes. A set of reliable experimental data is necessary for conducting such intercomparison and validation exercises. Experimental results from a large-loss of coolant accident (LOCA) test simulating HWR LOCA behaviour that was conducted by Atomic Energy of Canada Ltd. (AECL) was selected for this validation project. This report provides a comparison of the results obtained from six participating countries, utilizing four different computer codes. General conclusions are reached and recommondations made.
Download or read book Heavy Water Reactor Moderator Effectiveness as a Backup Heat Sink During Accidents written by International Atomic Energy Agency and published by . This book was released on 2019 with total page 83 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Analysis of Severe Accidents in Pressurized Heavy Water Reactors written by Author) and published by . This book was released on 2008 with total page 146 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report instructs the reader on how to perform deterministic analysis of severe accidents in pressurized heavy water reactors (PHWRs) by means of available computer codes. The analysis of accident phenomena should assist in the development of practicable preventive or mitigatory measures. In addition to providing a framework for data collection and analysis relevant to both the in- and ex-vessel phases of severe accidents, the publication also provides guidance for severe accident management.
Download or read book Thermal Hydraulic Performance Analysis of a Small Integral Pressurized Water Reactor Core written by Stuart Ryan Blair and published by . This book was released on 2003 with total page 257 pages. Available in PDF, EPUB and Kindle. Book excerpt: A thermal hydraulic analysis of the International Reactor Innovative and Secure (IRIS) core has been performed. Thermal margins for steady state and a selection of Loss Of Flow Accidents have been assessed using three methodologies to account for uncertainty. The thermal hydraulic analysis has shown that the IRIS is designed with adequate thermal margin for steady state operation, the locked rotor/shaft shear accident (LR/SS) and for variants of the partial loss of flow accident. To treat uncertainties, three methods were used, ranging from conservative, deterministic methods, to more realistic and computationally demanding Monte Carlo-based methods. To facilitate the computational requirements of the thermal hydraulic analysis, a script-based interface was created for VIPRE. This scripted interface (written in Matlab) supplants the existing file-based interface. This interface allows for repeated, automatic execution of the VIPRE code on a script-modifiable input data, and parses and stores output data to disk. This endows the analyst with much greater power to use VIPRE in parametric studies, or using the Monte Carlo-based uncertainty analysis methodology. The Matlab environment also provides powerful visualization capability that greatly eases the task of data analysis.
