Evaluation of Severe Accident Risks: Quantification of Major Input Parameters: Expert Opinion Elicitation on In-Vessel Issues (Vol. 2, Rev.1)

Technical Report · Sat Dec 01 04:00:00 EST 1990

DOI:https://doi.org/10.2172/6286229· OSTI ID:6286229

Harper, F. T. ^[1]; Breeding, R. J. ^[1]; Brown, T. D. ^[1]; Gregory, J. J. ^[1]; Payne, A. C. ^[1]; Gorham, E. D. ^[1]; Amos, Christopher N. ^[2]

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1. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
2. Science Applications International Corporation, Albuquerque, NM (United States)

This report records part of the vast amount of information received during the expert judgment elicitation process that took place in support of the NUREG-1150 effort sponsored by the US Nuclear Regulatory Commission. The results of the In-Vessel Expert Panel are presented in this part of Volume 2 of NUREG/CR-4551. The In-Vessel Panel considered six issues: temperature-induced pressurized water reactor (PWR) hot leg or surge line failure before vessel breach; temperature-induced steam generator tube rupture (SGTR) before vessel breach; boiling water reactor (BWR) in-vessel hydrogen production; BWR bottom head failure; PWR in-vessel hydrogen generation; and PWR bottom head failure.

• 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: 6286229
• Report Number(s): NUREG/CR--4551-Vol.2-Rev.1-Pt.1; SAND--86-1309-Vol.2-Rev.1-Pt.1; ON: TI91005989
• Country of Publication: United States
• Language: English

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NONMETALS
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