MELCOR Analyses for Accident Progression Issues

Technical Report · Mon Dec 31 23:00:00 EST 1990

DOI:https://doi.org/10.2172/6051232· OSTI ID:6051232

Dingman, S. E. ^[1]; Shaffer, C. J. ^[1]; Payne, A. C. ^[1]; Carmel, M. K. ^[1]

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1. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

Results of calculations performed with MELCOR and HECTR in support of the NUREG-1150 study are presented in this report. The analyses examined a wide range of issues. The analyses included integral calculations covering an entire accident sequence, as well as calculations that addressed specific issues that could affect several accident sequences. The results of the analyses for Grand Gulf, Peach Bottom, LaSalle, and Sequoyah are described, and the major conclusions are summarized.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research; Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)
• Sponsoring Organization: USNRC; USDOE
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6051232
• Report Number(s): NUREG/CR--5331; SAND--89-0072; ON: TI91007247
• Country of Publication: United States
• Language: English

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