Innovative Double-Wall Bayonet Tubes HX for DHR System in LFR
Description
Conclusions: ⇨ Integral Circulation Experiments are carried out to reproduce the thermal hydraulic behaviour of a HLM pool-type nuclear reactor primary flow path. ⇨ The test section has been designed coupling an high performance heat source with a prototypical heat exchanger (ELSYW-DHR prototype). ⇨ Steady state full power tests have been run, allowing to obtain first results. ⇨ The results carried out allowed to verify the performance of the W-DHR proposed for ELSY. It allow to achieve the goals defined. ⇨ Several tests have been planned (2012) to complete the characterization of the W-DHR component under transient condition (start-up, shut down). The ICE test section has been properly up-graded for this aim (and not only). ⇨ Integral Circulation Experiments will contribute to the demonstration of the HLM pool-type nuclear reactor feasibility (pool-thermal hydraulic assessment, technological feasibility)
Files
45084439.pdf
Files
(5.4 MB)
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Additional details
Identifiers
Publishing Information
- Imprint Title
- IAEA Technical Meeting on Innovative Heat Exchanger and Steam Generator Designs for Fast Reactors. Presentations
- Imprint Pagination
- vp.
- Journal Page Range
- 42 p.
- Report number
- IAEA-TM--40938(presentations)
Conference
- Title
- IAEA Technical Meeting on Innovative Heat Exchanger and Steam Generator Designs for Fast Reactors
- Dates
- 21-22 Dec 2011
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 45084439
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN; HEAT EXCHANGERS; HEAT SOURCES; REACTOR START-UP; REACTORS; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- FLUID MECHANICS; HYDRAULICS; MECHANICS; START-UP
Optional Information
- Notes
- PowerPoint presentation Imprint:Conducted within the framework of IAEA Nuclear Energy Department#Right Single Quotation Mark#s Technical Working Group on Fast Reactors (TWG-FR)