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Accident Source Terms for Light-Water Nuclear Power Plants (NUREG-1465) - Final ReportOn this page: Download complete document The following links on this page are to documents in Adobe Portable Document Format (PDF). See our Plugins, Viewers, and Other Tools page for more information. For successful viewing of PDF documents on our site please be sure to use the latest version of Adobe. Publication InformationManuscript Completed: February 1995 L Soffer, S. B. Burson, C. M. Ferrell, Division of Systems Technology AbstractIn 1962 The U.S. Atomic Energy Commission published
TLD-14844, "Calculation of Distance Factors for Power
and Test Reactors" which specified a release of fission
products from the core to the reactor containment in
the event of a postulated accident involving a "substantial meltdown of the core." This "source term,"
the basis for the NRC's Regulatory guides 1.3 and 1.4,
has been used to determine compliance with the 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 |
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