Accident source terms for light-water nuclear power plants using high-burnup or MOX fuel. Metadata

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Title

  • Main Title Accident source terms for light-water nuclear power plants using high-burnup or MOX fuel.

Creator

  • Author: Salay, Michael (U.S. Nuclear Regulatory Commission, Washington, D.C.)
    Creator Type: Personal
  • Author: Gauntt, Randall O.
    Creator Type: Personal
  • Author: Lee, Richard Y. (U.S. Nuclear Regulatory Commission, Washington, D.C.)
    Creator Type: Personal
  • Author: Powers, Dana Auburn
    Creator Type: Personal
  • Author: Leonard, Mark Thomas
    Creator Type: Personal

Contributor

  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization

Publisher

  • Name: Sandia National Laboratories
    Place of Publication: United States

Date

  • Creation: 2011-01-01

Language

  • English

Description

  • Content Description: 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.
  • Physical Description: 60 p.

Subject

  • Keyword: Statistics
  • Keyword: Molybdates
  • Keyword: Source Terms
  • Keyword: Reactor Accidents
  • Keyword: Molybdenum
  • Keyword: Heat Losses
  • Keyword: Radioisotopes
  • Keyword: Containment
  • Keyword: Reactor Cores
  • Keyword: Fission Products
  • Keyword: Physics
  • Keyword: Tellurium
  • Keyword: Computer Codes
  • Keyword: Accidents
  • Keyword: Cesium
  • Keyword: Meltdown
  • Keyword: Nuclear Power Plants
  • STI Subject Categories: 21 Specific Nuclear Reactors And Associated Plants
  • Keyword: Burnup

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report

Format

  • Text

Identifier

  • Report No.: SAND2011-0128
  • Grant Number: AC04-94AL85000
  • DOI: 10.2172/1010412
  • Office of Scientific & Technical Information Report Number: 1010412
  • Archival Resource Key: ark:/67531/metadc834935