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Book CONTAINMENT EVENT ANALYSIS FOR POSTULATED SEVERE ACCIDENTS SURRY POWER STATION UNIT 1

Download or read book CONTAINMENT EVENT ANALYSIS FOR POSTULATED SEVERE ACCIDENTS SURRY POWER STATION UNIT 1 written by A. S. Benjamin and published by . This book was released on 1987 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Containment Event Analysis for Postulated Severe Accidents

Download or read book Containment Event Analysis for Postulated Severe Accidents written by C. N. Amos and published by . This book was released on 1987 with total page 350 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Containment Event Analysis for Postulated Severe Accidents

Download or read book Containment Event Analysis for Postulated Severe Accidents written by C. N. Amos and published by . This book was released on 1987 with total page 325 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Effects of Degradation on the Severe Accident Consequences for a Pwr Plant With a Reinforced Concrete Containment Vessel

Download or read book Effects of Degradation on the Severe Accident Consequences for a Pwr Plant With a Reinforced Concrete Containment Vessel written by U.s. Nuclear Reglatory Commission and published by CreateSpace. This book was released on 2014-05-22 with total page 94 pages. Available in PDF, EPUB and Kindle. Book excerpt: Various forms of degradation have been observed in the containment vessels of a number of operating nuclear power plants in the United States. Examples of degradation include corrosion of the steel shell or liner, corrosion of reinforcing bars and prestressing tendons, loss of prestressing, and corrosion of bellows. The containment serves as the ultimate barrier against the release of radioactive material into the environment. Because of this role, compromising the containment could increase the risk of a large release in the unlikely event of an accident. Previous work in this area has assessed the effects that degradation has on the pressure retaining capacity of the containment vessel through structural analysis that account for degradation. These analyses have provided useful information about the effects of the degradation on the structural capacity of the containment in both deterministic and probabilistic fashions. However, the appropriate metric to use in assessing containment degradation effects during a severe accident was determined to require additional study. The previous work with probabilistic descriptions of the containment capacity were obtained from the results of the structural analysis models, and used as input for the risk models (Probabilistic Risk Assessment analyses). The risk was formulated in terms of the large early release frequency (LERF). The relative LERF values were computed for various postulated cases of degradation. In that study, an instance of degradation was treated as a change in the plant's licensing basis and assessed with U.S. NRC Regulatory Guide 1.174, “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis.” The Regulatory Guide provides the limits of the acceptable increases in LERF due to changes in the plant. Many of the cases of postulated degradation were those consisting of local corrosion in the liner or shell that produce leaks that do not contribute significantly to LERF, and in some cases, cause no change in LERF. Early releases due to small leaks were found to contribute to the small early release frequency (SERF). Since Regulatory Guide 1.174 does not provide guidance on the limits of SERF, additional deterministic analyses were performed in this study to assess the effects of degradation on the consequences using metrics other than LERF. This study was performed using the Sandia codes MELCOR and MACCS. These codes were used to simulate two different accident scenarios (long- and short-term station black-outs) and compute the resulting consequences for a PWR plant with a reinforced concrete containment. The structural analyses used in the previous probabilistic study were used to develop the containment behavior models for the accident simulations. Several different postulated cases of liner corrosion were considered to enable a comparison of the consequences.

Book Proceedings of the Workshop on Containment Integrity

Download or read book Proceedings of the Workshop on Containment Integrity written by and published by . This book was released on 1986 with total page 608 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1995 with total page 782 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Title List of Documents Made Publicly Available

Download or read book Title List of Documents Made Publicly Available written by and published by . This book was released on 1985 with total page 588 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Monthly Catalogue United States Public Documents

Download or read book Monthly Catalogue United States Public Documents written by and published by . This book was released on 1989 with total page 1302 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Analysis of Core concrete Interaction Event with Flooding for the Advanced Neutron Source Reactor

Download or read book Analysis of Core concrete Interaction Event with Flooding for the Advanced Neutron Source Reactor written by and published by . This book was released on 1993 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper discusses salient aspects of the methodology, assumptions, and modeling of various features related to estimation of source terms from an accident involving a molten core-concrete interaction event (with and without flooding) in the Advanced Neutron Source (ANS) reactor at the Oak Ridge National Laboratory. Various containment configurations are considered for this postulated severe accident. Several design features (such as rupture disks) are examined to study containment response during this severe accident. Also, thermal-hydraulic response of the containment and radionuclide transport and retention in the containment are studied. The results are described as transient variations of source terms, which are then used for studying off-site radiological consequences and health effects for the support of the Conceptual Safety Analysis Report for ANS. The results are also to be used to examine the effectiveness of subpile room flooding during this type of severe accident.

Book Implications of the Accident at Chernobyl for Safety Regulation of Commercial Nuclear Power Plants in the United States

Download or read book Implications of the Accident at Chernobyl for Safety Regulation of Commercial Nuclear Power Plants in the United States written by and published by . This book was released on 1987 with total page 112 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Proceedings of the U S Nuclear Regulatory Commission Eleventh Water Reactor Safety Research Information Meeting Held at National Bureau of Standards Gaithersburg Maryland October 24 28 1983 Plenary session integral system experiments separate effects foreign programs in thermal hydraulics EPRI safety research

Download or read book Proceedings of the U S Nuclear Regulatory Commission Eleventh Water Reactor Safety Research Information Meeting Held at National Bureau of Standards Gaithersburg Maryland October 24 28 1983 Plenary session integral system experiments separate effects foreign programs in thermal hydraulics EPRI safety research written by and published by . This book was released on 1984 with total page 732 pages. Available in PDF, EPUB and Kindle. Book excerpt: