Published May 2010 | Version v1
Book

CFD primary loop analysis of the ELSY reactor with focus on decay heat removal

  • 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.)

Part of:
Annual meeting on nuclear technology 2010. Documentation

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)

Optional Information

Notes
Imprint:Jahrestagung Kerntechnik 2010. Dokumentation