The NOKO/TOPFLOW facility for natural convection flow
- 1. Institute for Safety and Reactor Technology, Forschungszentrum Juelich (Germany)
- 2. Institute for Safety Research, Forschungszentrum Rossendorf (Germany)
Description
For the study of the effectiveness of passive safety systems a high pressure (up to 7 MPa) and high power (up to 4 MW) test facility - named NOKO - has been constructed and operated at the Forschungszentrum Juelich. From 1996-1998 this facility was used for a project within the 4th FP of the EU 'European BWR R and D Cluster for Innovative Passive Safety Systems'. An overview and selected results are given for the tests with two bundles of the emergency condenser, with the building and plate condenser, with 4 different passive initiators, with a passive flooding system and with decay heat removal tests during shutdown. It has been decided to decrease substantially the safety research at the Forschungszentrum Juelich; to maintain the experimental competence for two-phase flow the NOKO facility will be transferred to the Forschungszentrum Rossendorf by the end of the year 2000 up to the beginning of the year 2001. The facility will be named TOPFLOW; the main objectives of future tests will be oriented towards more generic research: investigation of steady state and transient two-phase flow phenomena especially transient two-phase flow patterns, the development of two-phase flow instrumentation, the generation of a data basis for Computational Fluid Dynamic (CFD)-Code validation and testing of heat exchangers and safety systems. An overview will be given about the modifications and improvements related to the test facility and the planned tests. (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. 213-226
- 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
- 33018381
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; ENGINEERED SAFETY SYSTEMS; FLUID FLOW; NATURAL CONVECTION; STEADY FLOW; TEST FACILITIES; THERMAL ANALYSIS; TWO-PHASE FLOW; VALIDATION
- Descriptors DEC
- CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HEAT TRANSFER; MASS TRANSFER; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs, 16 figs