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Book Revised Accident Source Terms for Light water Reactors

Download or read book Revised Accident Source Terms for Light water Reactors written by and published by . This book was released on 1995 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper presents revised accident source terms for light-water reactors incorporating the severe accident research insights gained in this area over the last 15 years. Current LWR reactor accident source terms used for licensing date from 1962 and are contained in Regulatory Guides 1.3 and 1.4. These specify that 100% of the core inventory of noble gases and 25% of the iodine fission products are assumed to be instantaneously available for release from the containment. The chemical form of the iodine fission products is also assumed to be predominantly elemental iodine. These assumptions have strongly affected present nuclear air cleaning requirements by emphasizing rapid actuation of spray systems and filtration systems optimized to retain elemental iodine. A proposed revision of reactor accident source terms and some im implications for nuclear air cleaning requirements was presented at the 22nd DOE/NRC Nuclear Air Cleaning Conference. A draft report was issued by the NRC for comment in July 1992. Extensive comments were received, with the most significant comments involving (a) release fractions for both volatile and non-volatile species in the early in-vessel release phase, (b) gap release fractions of the noble gases, iodine and cesium, and (c) the timing and duration for the release phases. The final source term report is expected to be issued in late 1994. Although the revised source terms are intended primarily for future plants, current nuclear power plants may request use of revised accident source term insights as well in licensing. This paper emphasizes additional information obtained since the 22nd Conference, including studies on fission product removal mechanisms, results obtained from improved severe accident code calculations and resolution of major comments, and their impact upon the revised accident source terms. Revised accident source terms for both BWRS and PWRS are presented.

Book Revised Accident Source Terms for Light water Nuclear Power Plants

Download or read book Revised Accident Source Terms for Light water Nuclear Power Plants written by U.S. Nuclear Regulatory Commission. Office of the Secretary and published by . This book was released on 1992 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Accident Source Terms for Light Water Nuclear Power Plants  Final Report

Download or read book Accident Source Terms for Light Water Nuclear Power Plants Final Report written by and published by . This book was released on 1995 with total page 31 pages. Available in PDF, EPUB and Kindle. Book excerpt: In 1962 tile US Atomic Energy Commission published TID-14844, C̀̀alculation of Distance Factors for Power and Test Reactors̀̀ which specified a release of fission products from the core to the reactor containment for a postulated accident involving s̀̀ubstantial meltdown of the core.̀̀ This s̀̀ource term, ̀̀ tile basis for tile NRCs̀ Regulatory Guides 1.3 and 1.4, has been used to determine compliance with tile NRCs̀ reactor site criteria, 10 CFR Part 100, and to evaluate other important plant performance requirements. During the past 30 years substantial additional information on fission product releases has been developed based on significant severe accident research. This document utilizes this research by providing more realistic estimates of the s̀̀ource term ̀̀release into containment, in terms of timing, nuclide types, quantities and chemical form, given a severe core-melt accident. This revised s̀̀ource term ̀̀is to be applied to the design of future light water reactors (LWRs). Current LWR licensees may voluntarily propose applications based upon it.

Book Radionuclide Source Terms from Severe Accidents to Nuclear Power Plants with Light Water Reactors

Download or read book Radionuclide Source Terms from Severe Accidents to Nuclear Power Plants with Light Water Reactors written by International Nuclear Safety Advisory Group and published by Bernan Press(PA). This book was released on 1987 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report presents the views of the IAEA's International Nuclear Safety Advisory Group INSAG on the source term issue for LWRs of existing designs. The report considers the present status of source term research and analysis and their implications. It identifies problems which remain to be resolved and indicates areas where work should be initiated to improve safety.

Book Nuclear Safety in Light Water Reactors

Download or read book Nuclear Safety in Light Water Reactors written by Bal Raj Sehgal and published by Academic Press. This book was released on 2012-01-05 with total page 732 pages. Available in PDF, EPUB and Kindle. Book excerpt: La 4e de couverture indique : Organizes and presents all the latest thought on LWR nuclear safety in one consolidated volume, provided by the top experts in the field, ensuring high-quality, credible and easily accessible information.

Book Accident Source Terms for Light Water Nuclear Power Plants

Download or read book Accident Source Terms for Light Water Nuclear Power Plants written by U.s. Nuclear Reglatory Commission and published by CreateSpace. This book was released on 2014-06-06 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt: In 1962, the Atomic Energy Commission issued Technical Information Document 14844, "Calculation of Distance Factor for Power and Test Reactors". In this document, a release of fission from the core of a light water reactor into the containment atmosphere was postulated for the purpose of calculating off-site doses in accordance with 10 CFR part 100.

Book Accident Tolerant Materials for Light Water Reactor Fuels

Download or read book Accident Tolerant Materials for Light Water Reactor Fuels written by Raul B. Rebak and published by Elsevier. This book was released on 2020-01-10 with total page 237 pages. Available in PDF, EPUB and Kindle. Book excerpt: Accident Tolerant Materials for Light Water Reactor Fuels provides a description of what an accident tolerant fuel is and the benefits and detriments of each concept. The book begins with an introduction to nuclear power as a renewable energy source and the current materials being utilized in light water reactors. It then moves on to discuss the recent advancements being made in accident tolerant fuels, reviewing the specific materials, their fabrication and implementation, environmental resistance, irradiation behavior, and licensing requirements. The book concludes with a look to the future of new power generation technologies. It is written for scientists and engineers working in the nuclear power industry and is the first comprehensive work on this topic. Introduces the fundamental description of accident tolerant fuel, including fabrication and implementation Describes both the benefits and detriments of the various Accident Tolerant Fuel concepts Includes information on the process of materials selection with a discussion of how and why specific materials were chosen, as well as why others failed

Book NUREG CR

    Book Details:
  • Author : U.S. Nuclear Regulatory Commission
  • Publisher :
  • Release : 1977
  • ISBN :
  • Pages : 48 pages

Download or read book NUREG CR written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1977 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Radioactive Gaseous Effluent Source Terms for Postulated Accident Conditions in Light water cooled Nuclear Power Plants

Download or read book Radioactive Gaseous Effluent Source Terms for Postulated Accident Conditions in Light water cooled Nuclear Power Plants written by W. L. Slagle and published by . This book was released on 1978 with total page 126 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Accident Source Terms for Light water Nuclear Power Plants Using High burnup Or MOX Fuel

Download or read book Accident Source Terms for Light water Nuclear Power Plants Using High burnup Or MOX Fuel written by and published by . This book was released on 2011 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt: Representative accident source terms patterned after the NUREG-1465 Source Term have been developed for high burnup fuel in BWRs and PWRs and for MOX fuel in a PWR with an ice-condenser containment. These source terms have been derived using nonparametric order statistics to develop distributions for the timing of radionuclide release during four accident phases and for release fractions of nine chemical classes of radionuclides as calculated with the MELCOR 1.8.5 accident analysis computer code. The accident phases are those defined in the NUREG-1465 Source Term - gap release, in-vessel release, ex-vessel release, and late in-vessel release. Important differences among the accident source terms derived here and the NUREG-1465 Source Term are not attributable to either fuel burnup or use of MOX fuel. Rather, differences among the source terms are due predominantly to improved understanding of the physics of core meltdown accidents. Heat losses from the degrading reactor core prolong the process of in-vessel release of radionuclides. Improved understanding of the chemistries of tellurium and cesium under reactor accidents changes the predicted behavior characteristics of these radioactive elements relative to what was assumed in the derivation of the NUREG-1465 Source Term. An additional radionuclide chemical class has been defined to account for release of cesium as cesium molybdate which enhances molybdenum release relative to other metallic fission products.

Book Accident Source Terms for Boiling Water Reactors with High Burnup Cores

Download or read book Accident Source Terms for Boiling Water Reactors with High Burnup Cores written by and published by . This book was released on 2007 with total page 126 pages. Available in PDF, EPUB and Kindle. Book excerpt: The primary objective of this report is to provide the technical basis for development of recommendations for updates to the NUREG-1465 Source Term for BWRs that will extend its applicability to accidents involving high burnup (HBU) cores. However, a secondary objective is to re-examine the fundamental characteristics of the prescription for fission product release to containment described by NUREG-1465. This secondary objective is motivated by an interest to understand the extent to which research into the release and behaviors of radionuclides under accident conditions has altered best-estimate calculations of the integral response of BWRs to severe core damage sequences and the resulting radiological source terms to containment. This report, therefore, documents specific results of fission product source term analyses that will form the basis for the HBU supplement to NUREG-1465. However, commentary is also provided on observed differences between the composite results of the source term calculations performed here and those reflected NUREG-1465 itself.

Book Accident Source Terms for Pressurized Water Reactors with High burnup Cores Calculated Using MELCOR 1 8 5

Download or read book Accident Source Terms for Pressurized Water Reactors with High burnup Cores Calculated Using MELCOR 1 8 5 written by and published by . This book was released on 2010 with total page 99 pages. Available in PDF, EPUB and Kindle. Book excerpt: In this study, risk-significant pressurized-water reactor severe accident sequences are examined using MELCOR 1.8.5 to explore the range of fission product releases to the reactor containment building. Advances in the understanding of fission product release and transport behavior and severe accident progression are used to render best estimate analyses of selected accident sequences. Particular emphasis is placed on estimating the effects of high fuel burnup in contrast with low burnup on fission product releases to the containment. Supporting this emphasis, recent data available on fission product release from high-burnup (HBU) fuel from the French VERCOR project are used in this study. The results of these analyses are treated as samples from a population of accident sequences in order to employ approximate order statistics characterization of the results. These trends and tendencies are then compared to the NUREG-1465 alternative source term prescription used today for regulatory applications. In general, greater differences are observed between the state-of-the-art calculations for either HBU or low-burnup (LBU) fuel and the NUREG-1465 containment release fractions than exist between HBU and LBU release fractions. Current analyses suggest that retention of fission products within the vessel and the reactor coolant system (RCS) are greater than contemplated in the NUREG-1465 prescription, and that, overall, release fractions to the containment are therefore lower across the board in the present analyses than suggested in NUREG-1465. The decreased volatility of Cs2MoO4 compared to CsI or CsOH increases the predicted RCS retention of cesium, and as a result, cesium and iodine do not follow identical behaviors with respect to distribution among vessel, RCS, and containment. With respect to the regulatory alternative source term, greater differences are observed between the NUREG-1465 prescription and both HBU and LBU predictions than exist between HBU and LBU analyses. Additionally, current analyses suggest that the NUREG-1465 release fractions are conservative by about a factor of 2 in terms of release fractions and that release durations for in-vessel and late in-vessel release periods are in fact longer than the NUREG-1465 durations. It is currently planned that a subsequent report will further characterize these results using more refined statistical methods, permitting a more precise reformulation of the NUREG-1465 alternative source term for both LBU and HBU fuels, with the most important finding being that the NUREG-1465 formula appears to embody significant conservatism compared to current best-estimate analyses.