Best-judgment analysis of emergency core cooling system performance. [PWR]

Journal Article · Fri Jul 01 04:00:00 EDT 1977 · Nucl. Technol.; (United States)

OSTI ID:7306554

Kessler, T C; Fader, G B

The requirements for an emergency core cooling system (ECCS) evaluation model that is acceptable for a pressurized water reactor licensing analysis are detailed in Appendix K to 10CFR50. The purpose of these requirements is to ensure that such an analysis will yield a conservative upper bound to the maximum cladding temperature and cladding oxidation that can result from a postulated loss-of-coolant accident (LOCA). By its nature, therefore, this model is inappropriate to indicate the actual anticipated results of a LOCA. Furthermore, a quantitative assessment of the conservatism inherent in the licensing model is unavailable. To produce realistic LOCA results, a calculation was performed at Combustion Engineering (C-E) for the reactor in its System 80/sup TM/ nuclear steam supply system, using a best-judgment ECCS evaluation model. The best-judgment model is a C-E first-generation best-estimate model that uses the basic Appendix K licensing computer programs, but in which the bounding conservatisms required by Appendix K are relaxed for selected parameters and models of primary concern in a LOCA analysis. The important differences between the best-judgment model and the Appendix K licensing model are examined.

• Research Organization: Combustion Engineering, Inc., Windsor, CT
• OSTI ID: 7306554
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 34:2; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CE STANDARD REACTOR
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PERFORMANCE
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS