Change search
ReferencesLink to record
Permanent link

Direct link
Modelling of stationary fluctuations in nuclear reactor cores in the frequency domain
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
2015 (English)In: Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, American Nuclear Society, 2015, 2406-2419 p.Conference paper (Refereed)Text
Abstract [en]

This paper presents the development of a numerical tool to simulate the effect of stationary fluctuations in Light Water Reactor cores. The originating fluctuations are defined for the variables describing the boundary conditions of the system, i.e. inlet velocity, inlet enthalpy, and outlet pressure. The tool calculates the three-dimensional space-frequency distributions within the core of the corresponding fluctuations in neutron flux, coolant density, coolant velocity, coolant enthalpy, and fuel temperature. The tool is thus based on the simultaneous modelling of neutron transport, fluid dynamics, and heat transfer in a truly integrated and fully coupled manner. The modelling of neutron transport relies on the two-group diffusion approximation and a spatial discretization based on finite differences. The modelling of fluid dynamics is performed using the homogeneous equilibrium model complemented with pre-computed static slip ratio. Heat conduction in the fuel pins is also accounted for, and the heat transfer between the fuel pins and the coolant is modelled also using a pre-computed distribution of the heat transfer coefficient. The spatial discretization of the fluid dynamic and heat transfer problems is carried out using finite volumes. The tool is currently entirely Matlab based with input data provided by an external static core simulator. The paper also presents the results of dynamic simulations performed for a typical pressurized water reactor and for a typical boiling water reactor, as illustrations of the capabilities of the tool.

Place, publisher, year, edition, pages
American Nuclear Society, 2015. 2406-2419 p.
Keyword [en]
Fluid dynamics, Heat transfer, LWR multi-physics, Neutron transport, Noise analysis, Boiling water reactors, Coolants, Diffusion in liquids, Enthalpy, Frequency domain analysis, Fuels, Heat conduction, Light water reactors, MATLAB, Monte Carlo methods, Neutron flux, Nuclear reactors, Pressurized water reactors, Reactor cores, Two phase flow, Diffusion approximations, Heat transfer problems, Homogeneous equilibrium models, Multi-physics, Spatial discretizations, Three dimensional space, Transport properties
National Category
Energy Engineering
Identifiers
URN: urn:nbn:se:kth:diva-181646ScopusID: 2-s2.0-84949490297ISBN: 9781510808041OAI: oai:DiVA.org:kth-181646DiVA: diva2:902415
Conference
Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, 19 April 2015 through 23 April 2015
Note

QC 20160211

Available from: 2016-02-11 Created: 2016-02-02 Last updated: 2016-02-11Bibliographically approved

Open Access in DiVA

No full text

Scopus

Search in DiVA

By author/editor
Hernández-Solís, Augusto
By organisation
Nuclear Power Safety
Energy Engineering

Search outside of DiVA

GoogleGoogle Scholar
The number of downloads is the sum of all downloads of full texts. It may include eg previous versions that are now no longer available

Total: 13 hits
ReferencesLink to record
Permanent link

Direct link