Containment performance of prototypical reactor containments subjected to severe accident conditions

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In SECY-90-016, the NTRC proposed a safety goal of a conditional containment failure probability (CCFP) of 0.1 and the alternative acceptance criteria allowed for steel containments, which specifies that the stresses should not exceed ASNE Level C allowables for severe accident pressures and temperatures. In this work, the need for an equivalent criterion for concrete containments was studied. Six surrogate containments were designed and analyzed in order to compare the margins between design pressure, pressure resulting in exceedance of Level C (or yield) stress limits, and ultimate pressure. For comparability, each containment has an identical internal volume and design pressure. ... continued below

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125 p.

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Klamerus, E.W.; Bohn, M.P.; Wesley, D.A. & Krishnaswamy, C.N. December 1, 1996.

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Description

In SECY-90-016, the NTRC proposed a safety goal of a conditional containment failure probability (CCFP) of 0.1 and the alternative acceptance criteria allowed for steel containments, which specifies that the stresses should not exceed ASNE Level C allowables for severe accident pressures and temperatures. In this work, the need for an equivalent criterion for concrete containments was studied. Six surrogate containments were designed and analyzed in order to compare the margins between design pressure, pressure resulting in exceedance of Level C (or yield) stress limits, and ultimate pressure. For comparability, each containment has an identical internal volume and design pressure. Results from the analysis showed margins to yield are comparable and display a similar margin for both steel and concrete containments. In addition, the margin to failure, although slightly higher in the steel containments, were also comparable. Finally, a CCFP for code design was determined based on general membrane behavior and imposing an upper bound severe accident curve developed in the DCH studies. The resulting CCFP`s were less then 0.02 (or 2%) for all the surrogate containments studied, showing that these containment designs all achieved the NRC safety goal.

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125 p.

Notes

INIS; OSTI as TI97001759

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  • Other Information: PBD: Dec 1996

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  • Other: TI97001759
  • Report No.: NUREG/CR--6433
  • Report No.: SAND--96-2445
  • Grant Number: AC04-94AL85000
  • DOI: 10.2172/431187 | External Link
  • Office of Scientific & Technical Information Report Number: 431187
  • Archival Resource Key: ark:/67531/metadc677371

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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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  • December 1, 1996

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  • July 25, 2015, 2:20 a.m.

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  • April 8, 2016, 8:19 p.m.

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Klamerus, E.W.; Bohn, M.P.; Wesley, D.A. & Krishnaswamy, C.N. Containment performance of prototypical reactor containments subjected to severe accident conditions, report, December 1, 1996; Washington D.C.. (digital.library.unt.edu/ark:/67531/metadc677371/: accessed October 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.