CFD Model Development and validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications

Technical Report · Mon Jul 14 04:00:00 EDT 2014

DOI:https://doi.org/10.2172/1159384· OSTI ID:1159384

Hassan, Yassin ^[1]; Corradini, Michael; Tokuhiro, Akira; Wei, Thomas Y.C.

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1. Univ. of Wisconsin, Madison, WI (United Texas A & M Univ., College Station, TX (United States); Nuclear Energy University Programs

The Reactor Cavity Cooling Systems (RCCS) is a passive safety system that will be incorporated in the VTHR design. The system was designed to remove the heat from the reactor cavity and maintain the temperature of structures and concrete walls under desired limits during normal operation (steady-state) and accident scenarios. A small scale (1:23) water-cooled experimental facility was scaled, designed, and constructed in order to study the complex thermohydraulic phenomena taking place in the RCCS during steady-state and transient conditions. The facility represents a portion of the reactor vessel with nine stainless steel coolant risers and utilizes water as coolant. The facility was equipped with instrumentation to measure temperatures and flow rates and a general verification was completed during the shakedown. A model of the experimental facility was prepared using RELAP5-3D and simulations were performed to validate the scaling procedure. The experimental data produced during the steady-state run were compared with the simulation results obtained using RELAP5-3D. The overall behavior of the facility met the expectations. The facility capabilities were confirmed to be very promising in performing additional experimental tests, including flow visualization, and produce data for code validation.

• Research Organization: Texas A & M Univ., College Station, TX (United States); Argonne National Lab. (ANL), Argonne, IL (United States); Univ. of Idaho, Moscow, ID (United States); Univ. of Wisconsin, Madison, WI (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE). Nuclear Energy University Programs (NEUP)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1159384
• Report Number(s): DOE/NEUP--09-817
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CAVITIES
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
CONCRETES
ENGINEERED SAFETY SYSTEMS
EXPERIMENTAL DATA
FLOW RATE
FLOW VISUALIZATION
FLUID MECHANICS
HTGR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COOLING SYSTEMS
REACTOR VESSELS
STEADY-STATE CONDITIONS
TRANSIENTS
VALIDATION
VERIFICATION
WALLS
WATER COOLED REACTORS