Natural circulation cooling in US Pressurized Water Reactors

Technical Report · Wed Jan 01 04:00:00 EST 1992

OSTI ID:10115403

McHugh, P R; Hentzen, R D ^[1]

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1. EG and G Idaho, Inc., Idaho Falls, ID (United States)

This document is a synthesis of data and analysis concerning natural circulation cooling in US Pressurized Water Reactors during off-normal operation and accident transients. Its objective is the integration of important research findings concerning PWR natural circulation phenomena into a single reference document. Sources of information include the Nuclear Regulatory Commission, reactor vendors, utility sponsored research groups, utilities, national laboratories, research reports, meeting papers, archival literature, and foreign sources. Three modes of natural circulation are discussed: single-phase, two-phase, and reflux/boiling condensation. General characteristics, analytical expressions, noncondensible gas effects, secondary effects, and nonuniform flow are described with regard to each of the natural circulation modes. Plant operational data, tests in scaled experimental facilities, and analysis with thermal hydraulic system codes have demonstrated the effectiveness of single-phase natural circulation as a cooling mechanism. Evidence suggests that two-phase natural circulation and reflux/boiling condensation can also be effective methods of alternate core cooling. Experimental test facility data and analysis are the primary components of the two-phase and reflux/boiling condensation natural circulation knowledge base.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 10115403
• Report Number(s): NUREG/CR--5769; EGG--2653; ON: TI92006862
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
BOILING
CONDENSATES
HEAT TRANSFER
HYDRAULICS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
T CODES
TRANSIENTS
TWO-PHASE FLOW