CFD primary loop analysis of the ELSY reactor with focus on decay heat removal
Creators
- 1. Karlsruher Institut fuer Technologie, Eggenstein-Leopoldshafen (Germany). Inst. fuer Neutronenphysik und Reaktortechnik
Description
Commercial CFD tools - such as ANSYS CFX - in connection with the present computational power - mainly by parallel computations - provide the possibility to obtain detailed 3D simulations even for cases with a complex geometry. In this work a detailed model of the ELSY (European Lead cooled System) reactor concept is presented which takes all parts of the reactor vessel into account. As it is not possible to represent all relevant parts in detail, loss coefficients and source terms for momentum and energy - as for the pumps, steam generators and the core- are used in combination with porous media approaches which are obtained from standalone high detailed CFD simulations or from system tools. The intention of this work is to investigate decay heat removal scenarios as consequence of a reactor shutdown. The investigation of the several cooling systems has shown that in case of decay heat removal by IC (Isolation Condenser) systems lead freezing in the lower part of the SG's (Steam Generators) may occur. (orig.)
Additional details
Additional titles
- Original title (English)
- Jahrestagung Kerntechnik 2010. Dokumentation
Publishing Information
- Publisher
- Inforum Verlag
- Imprint Place
- Bonn (Germany)
- Imprint Title
- Annual meeting on nuclear technology 2010. Documentation
- Imprint Pagination
- 1017 p.
- Journal Page Range
- 6 p.
Conference
- Title
- Annual meeting on nuclear technology 2010
- Original Conference Title
- Jahrestagung Kerntechnik 2010
- Dates
- 4-6 May 2010
- Place
- Berlin (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 43018324
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; AFTER-HEAT REMOVAL; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; DESIGN; FLUID MECHANICS; LEAD; LIQUID METAL COOLED REACTORS; NATURAL CONVECTION; NUMERICAL ANALYSIS; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR SHUTDOWN; REACTOR VESSELS; SOURCE TERMS; STEAM CONDENSERS; STEAM GENERATORS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- BOILERS; COMPUTER CODES; CONTAINERS; CONVECTION; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; ENERGY TRANSFER; HEAT TRANSFER; MASS TRANSFER; MATHEMATICS; MECHANICS; METALS; REACTOR COMPONENTS; REACTORS; REMOVAL; SHUTDOWN; SIMULATION; VAPOR CONDENSERS; VAPOR GENERATORS
Optional Information
- Notes
- Imprint:Jahrestagung Kerntechnik 2010. Dokumentation