skip to main content

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

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.
Authors:
 [1] ; ; ;
  1. Univ. of Wisconsin, Madison, WI (United Texas A & M Univ., College Station, TX (United States)
Publication Date:
OSTI Identifier:
1159384
Report Number(s):
DOE/NEUP--09-817
TRN: US1500395
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Research Org:
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 Org:
USDOE Office of Nuclear Energy (NE). Nuclear Energy University Programs (NEUP)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HTGR TYPE REACTORS; REACTOR COOLING SYSTEMS; VALIDATION; EXPERIMENTAL DATA; CAVITIES; CONCRETES; WATER COOLED REACTORS; COMPARATIVE EVALUATIONS; REACTOR VESSELS; STEADY-STATE CONDITIONS; COMPUTERIZED SIMULATION; R CODES; FLOW RATE; FLOW VISUALIZATION; REACTOR ACCIDENTS; ENGINEERED SAFETY SYSTEMS; TRANSIENTS; VERIFICATION; WALLS; FLUID MECHANICS