Published 2013 | Version v1
Miscellaneous Open

STAR-CD/CATHARE coupling methodology for thermal-hydraulic calculations on primary loop and heat exchangers in sodium-cooled fast reactor

  • 1. AREVA NP (France)

Description

Over the last two years, a coupling methodology between CATHARE and STAR-CD has been developed: • Thermal-hydraulic coupling through Inlet / Pressure boundaries; • Thermal coupling through Wall boundaries; • Implemented for sodium fast reactor calculations. The methodology is functional: • Validation on analytical case; • Implementation on FBR geometry and steam generator case; • Possibility of calculations with significant space and time scales (reactor scale, up to 6h) within an acceptable range of CPU time (~a few days) for industrial purposes (engineering studies support). Further validation required: → Benchmark with other CFD simulations; → Comparison with experimental data : natural convection end-of-life Phenix tests (in progress)

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Part of:
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13). Presentations

Additional details

Publishing Information

Publisher
IAEA
Imprint Place
Vienna (International Atomic Energy Agency (IAEA))
Imprint Title
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13). Presentations
Imprint Pagination
vp.
Journal Page Range
20 p.
Report number
IAEA-CN--199

Conference

Title
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios
Acronym
FR13
Dates
4-7 Mar 2013
Place
Paris (France)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
45089621
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENCHMARKS; COUPLING; ENGINEERING; FAST REACTORS; HEAT EXCHANGERS; NATURAL CONVECTION; SIMULATION; SODIUM; SODIUM COOLED REACTORS; STEAM GENERATORS; THERMAL HYDRAULICS
Descriptors DEC
ALKALI METALS; BOILERS; CONVECTION; ELEMENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; LIQUID METAL COOLED REACTORS; MASS TRANSFER; MECHANICS; METALS; REACTORS; VAPOR GENERATORS

Optional Information

Notes
PowerPoint presentation
Secondary number(s)
IAEA-CN--199/363