The VVER 440/230 confinement upgrade scoping study
- Westinghouse Electric Corp., Pittsburgh, PA (United States)
The VVER 440/230 nuclear power stations are currently being examined for safety improvements to meet internationally accepted safety criteria. Westinghouse has performed scoping analyses to evaluate different conceptual designs for modernization of the confinement systems. These designs represent alternatives for maintaining the confinement pressure below the 1-bar gauge (0.1-MPa) design pressure following a postulated loss-of-coolant accident (LOCA). These conceptual designs included the following: (1) adding a filtered vent to provide a release path to the atmosphere; (2) adding an auxiliary expansion volume to contain the mass and energy release; (3) adding an ice condenser unit to passively provide absorption of the energy released from the break. Each of these designs is intended to provide a means of handling the mass and energy released during the first 60 s of the LOCA. Thereafter, upgraded confinement spray and residual heat removal systems will provide the required pressure suppression and heat removal. Mass and energy release transients were generated for the VVER plant design for input into the confinement integrity evaluation. Three different hypothetical accidents were assumed: a 200- and 500-mm double-ended guillotine break and a 200-mm split break in the main reactor cooling piping. The transients were developed by scaling available best-estimate LOCA blowdown calculations and confirmed with RETRAN code calculations.
- OSTI ID:
- 5977072
- Report Number(s):
- CONF-910603--
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 63; ISSN TANSA; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220504 -- Nuclear Reactor Technology-- Environmental Aspects-- Design Basis & Hypothetical Accidents-- (1992-)
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
BOILERS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONDENSERS
CONTAINMENT
CONTAINMENT SYSTEMS
COOLING SYSTEMS
DESIGN
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
ENVIRONMENTAL IMPACTS
FISSION PRODUCT RELEASE
ICE CONDENSERS
LOSS OF COOLANT
MODIFICATIONS
POWER REACTORS
PRESSURE SUPPRESSION
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY
REACTORS
RHR SYSTEMS
SAFETY
SECONDARY COOLANT CIRCUITS
SIMULATION
STEAM CONDENSERS
STEAM GENERATORS
THERMAL REACTORS
VAPOR CONDENSERS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WWER TYPE REACTORS