CIRCUS and DESIRE: Experimental facilities for research on natural-circulation-cooled boiling water reactors
- 1. Interfaculty Reactor Institute, Delft University of Technology (Netherlands)
- 2. Kramers Laboratorium voor Fysische Technologie, Delf University of Technology (Netherlands)
Description
At the Delft University of Technology two thermohydraulic test facilities are being used to study the characteristics of Boiling Water Reactors (BWRs) with natural circulation core cooling. The focus of the research is on the stability characteristics of the system. DESIRE is a test facility with freon-12 as scaling fluid in which one fuel bundle of a natural-circulation BWR is simulated. The neutronic feedback can be simulated artificially. DESIRE is used to study the stability of the system at nominal and beyond nominal conditions. CIRCUS is a full-height facility with water, consisting of four parallel fuel channels and four parallel bypass channels with a common riser or with parallel riser sections. It is used to study the start-up characteristics of a natural-circulation BWR at low pressures and low power. In this paper a description of both facilities is given and the research items are presented. (author)
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Additional details
Publishing Information
- Imprint Title
- Natural circulation data and methods for advanced water cooled nuclear power plant designs. Proceedings of a technical committee meeting
- Imprint Pagination
- 252 p.
- Journal Page Range
- p. 207-212
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1281
Conference
- Title
- Technical committee meeting on natural circulation data and methods for advanced water cooled nuclear power plant designs
- Dates
- 18-21 Jul 2000
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 33018380
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COOLANT LOOPS; NATURAL CONVECTION; SIMULATION; TEST FACILITIES; THERMAL ANALYSIS
- Descriptors DEC
- CONVECTION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; MASS TRANSFER; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Refs, figs, tabs