skip to main content

SciTech ConnectSciTech Connect

Title: Thermal-Hydraulic Analysis of an Experimental Reactor Cavity Cooling System with Air. Part I: Experiments; Part II: Separate Effects Tests and Modeling

This experimental study investigates the thermal hydraulic behavior and the heat removal performance for a scaled Reactor Cavity Cooling System (RCCS) with air. A quarter-scale RCCS facility was designed and built based on a full-scale General Atomics (GA) RCCS design concept for the Modular High Temperature Gas Reactor (MHTGR). The GA RCCS is a passive cooling system that draws in air to use as the cooling fluid to remove heat radiated from the reactor pressure vessel to the air-cooled riser tubes and discharged the heated air into the atmosphere. Scaling laws were used to preserve key aspects and to maintain similarity. The scaled air RCCS facility at UW-Madison is a quarter-scale reduced length experiment housing six riser ducts that represent a 9.5° sector slice of the full-scale GA air RCCS concept. Radiant heaters were used to simulate the heat radiation from the reactor pressure vessel. The maximum power that can be achieved with the radiant heaters is 40 kW with a peak heat flux of 25 kW per meter squared. The quarter-scale RCCS was run under different heat loading cases and operated successfully. Instabilities were observed in some experiments in which one of the two exhaust ducts experienced a flowmore » reversal for a period of time. The data and analysis presented show that the RCCS has promising potential to be a decay heat removal system during an accident scenario.« less
Authors:
 [1] ;  [1] ;  [1] ;  [2] ;  [2] ;  [3] ;  [3]
  1. Univ. of Wisconsin, Madison, WI (United States). Dept. of Engineering Physics
  2. Texas A & M Univ., College Station, TX (United States)
  3. Univ. of Idaho, Moscow, ID (United States)
Publication Date:
OSTI Identifier:
1183658
Report Number(s):
DOE/NEUP--11-3079
11-3079; TRN: US1500402
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Research Org:
Univ. of Wisconsin, Madison, WI (United States); Texas A & M Univ., College Station, TX (United States); Univ. of Idaho, Moscow, ID (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; AIR; THERMAL HYDRAULICS; AFTER-HEAT REMOVAL; PRESSURE VESSELS; RADIANT HEATERS; TEMPERATURE RANGE 0400-1000 K; DESIGN; SIMULATION; HEAT FLUX; HEATING LOAD; SCALING LAWS; INSTABILITY; PERFORMANCE; RHR SYSTEMS; HTGR TYPE REACTORS; MODULAR STRUCTURES