Results from a scaled reactor cavity cooling system with water at steady state
- 1. Univ. of Wisconsin - Madison, 1500 Engineering Drive, Madison, WI 53706 (United States)
- 2. Univ. of Idaho - Moscow, Moscow, ID 83843 (United States)
Description
We present a summary of steady-state experiments performed with a scaled, water-cooled Reactor Cavity Cooling System (RCCS) at the Univ. of Wisconsin - Madison. The RCCS concept is used for passive decay heat removal in the Next Generation Nuclear Plant (NGNP) design and was based on open literature of the GA-MHTGR, HTR-10 and AVR reactor. The RCCS is a 1/4 scale model of the full scale prototype system, with a 7.6 m structure housing, a 5 m tall test section, and 1,200 liter water storage tank. Radiant heaters impose a heat flux onto a three riser tube test section, representing a 5 deg. radial sector of the actual 360 deg. RCCS design. The maximum heat flux and power levels are 25 kW/m2 and 42.5 kW, and can be configured for variable, axial, or radial power profiles to simulate prototypic conditions. Experimental results yielded measurements of local surface temperatures, internal water temperatures, volumetric flow rates, and pressure drop along the test section and into the water storage tank. The majority of the tests achieved a steady state condition while remaining single-phase. A selected number of experiments were allowed to reach saturation and subsequently two-phase flow. RELAP5 simulations with the experimental data have been refined during test facility development and separate effects validation of the experimental facility. This test series represents the completion of our steady-state testing, with future experiments investigating normal and off-normal accident scenarios with two-phase flow effects. The ultimate goal of the project is to combine experimental data from UW - Madison, UI, ANL, and Texas A and M, with system model simulations to ascertain the feasibility of the RCCS as a successful long-term heat removal system during accident scenarios for the NGNP. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-091-1
- Imprint Title
- Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12
- Imprint Pagination
- 2799 p.
- Journal Page Range
- p. 2274-2279
Conference
- Title
- 2012 International Congress on Advances in Nuclear Power Plants
- Acronym
- ICAPP '12
- Dates
- 24-28 Jun 2012
- Place
- Chicago, IL (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 44065661
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; AVR REACTOR; COMPUTERIZED SIMULATION; COOLING SYSTEMS; DESIGN; FLOW RATE; HEAT FLUX; HYPOTHETICAL ACCIDENTS; NUCLEAR POWER PLANTS; RADIANT HEATERS; SCALE MODELS; STEADY-STATE CONDITIONS; TANKS; TWO-PHASE FLOW; VALIDATION; WATER; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID FLOW; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEATERS; HELIUM COOLED REACTORS; HOMOGENEOUS REACTORS; HTGR TYPE REACTORS; HYDROGEN COMPOUNDS; NUCLEAR FACILITIES; OXYGEN COMPOUNDS; PEBBLE BED REACTORS; POWER PLANTS; POWER REACTORS; REACTORS; REMOVAL; SIMULATION; SOLID HOMOGENEOUS REACTORS; STRUCTURAL MODELS; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS; THORIUM REACTORS
Optional Information
- Notes
- 8 refs.