Published April 2002 | Version v1
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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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Natural circulation data and methods for advanced water cooled nuclear power plant designs. Proceedings of a technical committee meeting

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