Evaluation of containment failure modes and fission product releases during core meltdown accidents in a BWR with a Mark III containment

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An assessment is described of potential failure modes and fission product releases for a large number of postulated core meltdown accidents in a BWR with a Mark III containment. For this containment design, the most important failure mode was found to be due to hydrogen related phenomena. A one-dimensional lumped parameter computer code has been developed and used to determine the probability of various hydrogen phenomena for a range of postulated core meltdown sequences. Potential containment loads have been estimated and compared against the containment capacity to determine the probability of containment failure. The fission product release assessment began by ... continued below

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Pages: 14

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Ludewig, H.; Yu, W.S.; Jaung, R. & Pratt, W.T. January 1, 1985.

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Description

An assessment is described of potential failure modes and fission product releases for a large number of postulated core meltdown accidents in a BWR with a Mark III containment. For this containment design, the most important failure mode was found to be due to hydrogen related phenomena. A one-dimensional lumped parameter computer code has been developed and used to determine the probability of various hydrogen phenomena for a range of postulated core meltdown sequences. Potential containment loads have been estimated and compared against the containment capacity to determine the probability of containment failure. The fission product release assessment began by using the MARCH/CORRAL system of codes with key input parameters varied over a reasonable range. The parameters relate to primary system retention, re-emission, pool scrubbing, and fission product release in-vessel vs ex-vessel. The final step used more mechanistic calculations based on the system of codes recently developed under sponsorship of the Accident Source Term Program Office, NRC, and compares these predictions with the range of releases calculated in the sensitivity study.

Physical Description

Pages: 14

Notes

NTIS, PC A02/MF A01 - GPO.

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  • International ANS/ENS topical meeting on probabilistic safety methods and applications, San Francisco, CA, USA, 24 Feb 1985

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  • Other: TI86007124
  • Report No.: BNL-NUREG-37679
  • Report No.: CONF-850206-38
  • Grant Number: AC02-76CH00016
  • Office of Scientific & Technical Information Report Number: 6188199
  • Archival Resource Key: ark:/67531/metadc1107881

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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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  • January 1, 1985

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  • Feb. 22, 2018, 7:45 p.m.

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  • March 23, 2018, 2:12 p.m.

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Ludewig, H.; Yu, W.S.; Jaung, R. & Pratt, W.T. Evaluation of containment failure modes and fission product releases during core meltdown accidents in a BWR with a Mark III containment, article, January 1, 1985; United States. (digital.library.unt.edu/ark:/67531/metadc1107881/: accessed April 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.