Thermal-hydraulic effect of grid spacers and cladding rupture during reflood

Conference · Wed Jan 01 04:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6669492

Nithianandan, C K; Lowe, R J; Biller, J R ^[1]

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1. Babcock and Wilcox Co., Lynchburg, VA (United States)

Droplet breakup at grid spacers and at cladding swelled and ruptured locations plays an important role in the coolability of nuclear fuel rods during the reflooding period of a loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR). Models to simultate spacer grid effects and blockage and rupture effects on system thermal hydraulics were added to the B W Fuel Company's version of the RELAP5/MOD2 computer code. RELAP5/MOD2-B W was used to perform a postulated cold-leg large-break LOCA in a recirculating steam generator PWR. A summary of RELAP5 models and the PWR analysis results is presented in this paper.

• OSTI ID: 6669492
• Report Number(s): CONF-921102--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 66
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CODES
CORE FLOODING SYSTEMS
DROPLETS
ECCS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
FLUID MECHANICS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PARTICLES
POWER REACTORS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR INTERNALS
REACTOR PROTECTION SYSTEMS
REACTORS
RUPTURES
THERMAL ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS