Application of CFD Codes in Nuclear Reactor Safety Analysis
Joint Authors
Hoehne, Thomas
Rohde, U.
Krepper, E.
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2010, Issue 2010 (31 Dec. 2010), pp.1-8, 8 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2009-09-15
Country of Publication
Egypt
No. of Pages
8
Main Subjects
Engineering Sciences and Information Technology
Abstract EN
Computational Fluid Dynamics (CFD) is increasingly being used in nuclear reactor safety (NRS) analyses as a tool that enables safety relevant phenomena occurring in the reactor coolant system to be described in more detail.
Numerical investigations on single phase coolant mixing in Pressurised Water Reactors (PWR) have been performed at the FZD for almost a decade.
The work is aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution scenarios, and mixing phenomena of interest for economical operation and the structural integrity.
For the experimental investigation of horizontal two phase flows, different non pressurized channels and the TOPFLOW Hot Leg model in a pressure chamber was build and simulated with ANSYS CFX.
In a common project between the University of Applied Sciences Zittau/Görlitz and FZD the behaviour of insulation material released by a LOCA released into the containment and might compromise the long term emergency cooling systems is investigated.
Moreover, the actual capability of CFD is shown to contribute to fuel rod bundle design with a good CHF performance.
American Psychological Association (APA)
Hoehne, Thomas& Krepper, E.& Rohde, U.. 2009. Application of CFD Codes in Nuclear Reactor Safety Analysis. Science and Technology of Nuclear Installations،Vol. 2010, no. 2010, pp.1-8.
https://search.emarefa.net/detail/BIM-453929
Modern Language Association (MLA)
Hoehne, Thomas…[et al.]. Application of CFD Codes in Nuclear Reactor Safety Analysis. Science and Technology of Nuclear Installations No. 2010 (2010), pp.1-8.
https://search.emarefa.net/detail/BIM-453929
American Medical Association (AMA)
Hoehne, Thomas& Krepper, E.& Rohde, U.. Application of CFD Codes in Nuclear Reactor Safety Analysis. Science and Technology of Nuclear Installations. 2009. Vol. 2010, no. 2010, pp.1-8.
https://search.emarefa.net/detail/BIM-453929
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-453929