The effect of the number of condensed phases modeled on aerosol behavior during an induced steam generator tube rupture sequence

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Description

VICTORIA is a mechanistic computer code designed to analyze fission product behavior within a nuclear reactor coolant system (RCS) during a severe accident. It provides detailed predictions of the release of radioactive and nonradioactive materials from the reactor core and transport and deposition of these materials within the RCS. A recently completed independent peer review of VICTORIA, while confirming the overall adequacy of the code, recommended a number of modeling improvements. One of these recommendations, to model three rather than a single condensed phase, is the focus of the work reported here. The recommendation has been implemented as an option ... continued below

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21 p.

Creation Information

Bixler, N.E. & Schaperow, J.H. June 1, 1998.

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  • Bixler, N.E. Sandia National Labs., Albuquerque, NM (United States)
  • Schaperow, J.H. Nuclear Regulatory Commission, Washington, DC (United States)

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  • Sandia National Laboratories
    Publisher Info: Sandia National Labs., Albuquerque, NM (United States)
    Place of Publication: Albuquerque, New Mexico

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Description

VICTORIA is a mechanistic computer code designed to analyze fission product behavior within a nuclear reactor coolant system (RCS) during a severe accident. It provides detailed predictions of the release of radioactive and nonradioactive materials from the reactor core and transport and deposition of these materials within the RCS. A recently completed independent peer review of VICTORIA, while confirming the overall adequacy of the code, recommended a number of modeling improvements. One of these recommendations, to model three rather than a single condensed phase, is the focus of the work reported here. The recommendation has been implemented as an option so that either a single or three condensed phases can be treated. Both options have been employed in the study of fission product behavior during an induced steam generator tube rupture sequence. Differences in deposition patterns and mechanisms predicted using these two options are discussed.

Physical Description

21 p.

Notes

INIS; OSTI as DE98004425

Source

  • Specialist meeting on nuclear aerosols in reactor safety, Cologne (Germany), 16-18 Jun 1998

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  • Other: DE98004425
  • Report No.: SAND--98-0809C
  • Report No.: CONF-980640--
  • Grant Number: AC04-94AL85000
  • Office of Scientific & Technical Information Report Number: 645496
  • Archival Resource Key: ark:/67531/metadc697902

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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.

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Creation Date

  • June 1, 1998

Added to The UNT Digital Library

  • Aug. 14, 2015, 8:43 a.m.

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  • May 5, 2016, 8:28 p.m.

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Bixler, N.E. & Schaperow, J.H. The effect of the number of condensed phases modeled on aerosol behavior during an induced steam generator tube rupture sequence, article, June 1, 1998; Albuquerque, New Mexico. (digital.library.unt.edu/ark:/67531/metadc697902/: accessed October 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.