Accident Source Terms For Light - Water Nuclear Power Plants, Final Report, NUREG-1465, U.S. Nuclear Regulatory Commission, February 1995 PDF Download
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Languages : en
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Languages : en
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Category : Fission products
Languages : en
Pages : 30
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Author: U.S. Nuclear Regulatory Commission. Office of the Secretary
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Category : Fission products
Languages : en
Pages : 72
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Category :
Languages : en
Pages : 31
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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.
Author: U.s. Nuclear Reglatory Commission
Publisher: CreateSpace
ISBN: 9781500117344
Category : Science
Languages : en
Pages : 40
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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.
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Category : Fission products
Languages : en
Pages : 35
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Author: U.S. Nuclear Regulatory Commission
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Category : Nuclear energy
Languages : en
Pages : 48
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Category :
Languages : en
Pages : 10
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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.
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Category :
Languages : en
Pages : 60
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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.
Author: W. L. Slagle
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Category : Pressurized water reactors
Languages : en
Pages : 126
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