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| GENU2005-1 | Nuclear thermal hydraulics
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| Durée : | |
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| Crédits/ECTS : |
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| Titulaire(s) : | Yann Bartosiewicz |
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| Langue : | Langue anglaise |
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| Aperçu général : |
- Reactor heat generation
- Transport equations (single-phase & two-phase flow)
- Thermal analysis of fuel elements
- (Single-phase fluid mechanics and heat transfer)-usually already known
- Two-phase flow dynamics
- Two-phase heat transfer
- Single heated channel; steady state analysis
- Single heated channel; transient analysis
- Flow loops
- Utilisation of established codes.
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| Objectif du cours : |
- To be familiarised with various reactor types and their main design and operational
characteristics
- To learn how to estimate the volumetric heat generation rate in fission reactor cores under
normal operation and shutdown conditions
- To learn how to analyse the thermal performance of nuclear fuel elements
- To learn the basic fluid mechanics of single phase reactor cooling systems
- To learn to calculate pressure drop in reactor systems, including tube bundles, and spacer
grids
- To learn to analyse the heat transfer characteristics of single phase reactor cooling systems
- To learn the basic fluid mechanics of two-phase systems, including flow regime maps, void-quality relations, pressure drop, and critical flow
- To learn the fundamentals of boiling heat transfer, and its implications for reactor design
- To learn the fundamentals of core thermal design, with attention to design uncertainty
analysis and hot channel factors.
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| Organisation : |
- 2 t.m.
- SCK*CEN guidance for demonstrations with codes
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| Notes de cours : | Todreas, N.E. and Kazimi, M.S. Nuclear System I: Thermal Hydraulic Fundamentals, Hemisphere
Publishing Corp., New York, 1990.
Todreas, N. E. and Kazimi, M.S. Nuclear Systems II: Elements of Thermal Hydraulic Design,
Hemisphere Publishing Corp., New York, 1990.
Cumo, M. Impianti Nucleari, UTET,Torino, 1976. |
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| Contacts : | Katrien Van Tichelen: kvtichel@sckcen.be Marcel Weber: mweber@sckcen.be |
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