AP600 passive residual heat removal heat exchanger test

Conference · Mon Jan 01 04:00:00 EST 1990 · Transactions of the American Nuclear Society; (USA)

OSTI ID:5822274

Corletti, M M; Hochreiter, L E; Squarer, D

The AP600 reactor is a pressurized water reactor being designed to utilize a passive residual heat removal (PRHR) heat exchanger as the safety grade means for residual heat removal. The PRHR heat exchanger is utilized during many design basis events and is especially important in mitigating non-loss-of-coolant accidents such as loss of normal feedwater and feedwater line break. The PRHR system transfers decay heat from the reactor coolant system to the containment by heating and boiling the water in the in-containment refueling water storage tank (IRWST). The steam produced transfers heat to the atmosphere by condensing on the inside of the containment shell. The condensate is collected by gutters on the containment shell and is returned to the IRWST, which provides a heat sink for an indefinite amount of time. The PRHR test facility is a prototypical representation of the PRHR heat exchanger with respect to tube material, diameter, pitch, and tube length, such that the gravity-induced flow characteristics in the pool are representative of the design. The main scaling parameter for the pool is the pool volume per tube, which preserves the buoyancy and pool mixing effects. A generalized PRHR boiling correlation was developed using the approach given by Rohsenow such that pressure effects can be induced.

• OSTI ID: 5822274
• Report Number(s): CONF-901101--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 62
• Country of Publication: United States
• Language: English

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ACCIDENTS
AFTER-HEAT REMOVAL
BOILING
CONTAINMENT
CONTAINMENT SYSTEMS
CONTROL
CONVECTION
COOLING SYSTEMS
CRITICAL HEAT FLUX
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLOW RATE
FLUID MECHANICS
HEAT FLUX
HEAT SINKS
HEAT TRANSFER
HYDRAULICS
MASS TRANSFER
MATHEMATICAL MODELS
MEASURING INSTRUMENTS
MECHANICS
MITIGATION
MIXING
NATURAL CONVECTION
NUCLEATE BOILING
PASSIVITY
PERFORMANCE
PHASE TRANSFORMATIONS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
REMOVAL
RHR SYSTEMS
SAFETY
SINKS
STEAM
TEMPERATURE CONTROL
TEST FACILITIES
THERMOCOUPLES
WATER COOLED REACTORS
WATER MODERATED REACTORS