Accident source terms for Light-Water Nuclear Power Plants. Final report

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Description

In 1962 tile US Atomic Energy Commission published TID-14844, ``Calculation of Distance Factors for Power and Test Reactors`` which specified a release of fission products from the core to the reactor containment for a postulated accident involving ``substantial meltdown of the core``. This ``source term``, tile basis for tile NRC`s Regulatory Guides 1.3 and 1.4, has been used to determine compliance with tile NRC`s 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. ... continued below

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31 p.

Creation Information

Soffer, L.; Burson, S.B.; Ferrell, C.M.; Lee, R.Y. & Ridgely, J.N. February 1, 1995.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 140 times , with 6 in the last month . More information about this report can be viewed below.

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  • U.S. Nuclear Regulatory Commission
    Publisher Info: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology
    Place of Publication: Washington D.C.

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Description

In 1962 tile US Atomic Energy Commission published TID-14844, ``Calculation of Distance Factors for Power and Test Reactors`` which specified a release of fission products from the core to the reactor containment for a postulated accident involving ``substantial meltdown of the core``. This ``source term``, tile basis for tile NRC`s Regulatory Guides 1.3 and 1.4, has been used to determine compliance with tile NRC`s 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 ``source term`` release into containment, in terms of timing, nuclide types, quantities and chemical form, given a severe core-melt accident. This revised ``source term`` is to be applied to the design of future light water reactors (LWRs). Current LWR licensees may voluntarily propose applications based upon it.

Physical Description

31 p.

Notes

INIS; OSTI as TI95007966

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  • Other Information: PBD: Feb 1995

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  • Other: TI95007966
  • Report No.: NUREG--1465
  • DOI: 10.2172/29438 | External Link
  • Office of Scientific & Technical Information Report Number: 29438
  • Archival Resource Key: ark:/67531/metadc682260

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • February 1, 1995

Added to The UNT Digital Library

  • July 25, 2015, 2:20 a.m.

Description Last Updated

  • April 22, 2016, 6:34 p.m.

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Soffer, L.; Burson, S.B.; Ferrell, C.M.; Lee, R.Y. & Ridgely, J.N. Accident source terms for Light-Water Nuclear Power Plants. Final report, report, February 1, 1995; Washington D.C.. (https://digital.library.unt.edu/ark:/67531/metadc682260/: accessed July 21, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.