Published 1987 | Version v1
Miscellaneous Open

Modelling of pressurized water reactor fuel, rod time dependent radial heat flow with boundary element method

Creators

  • 1. Institut Jozef Stefan, Ljubljana (Yugoslavia)

Description

The basic principles of the boundary element method numerical treatment of the radial flow heat diffusion equation are presented. The algorithm copes the time dependent Dirichlet and Neumann boundary conditions, temperature dependent material properties and regions from different materials in thermal contact. It is verified on the several analytically obtained test cases. The developed method is used for the modelling of unsteady radial heat flow in pressurized water reactor fuel rod. (author)

Availability note (English)

Available from INIS in electronic form; Also available from the Institute of Nuclear Sciences VINCA

Files

38015828.pdf

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Additional details

Additional titles

Original title (Slovenian)
Modeliranje spremenljivega radijalnega toplotnega toka tlacnovodne gorivne palice z metodo robnih elementov

Publishing Information

Publisher
Society for Electronics,Telecommunications, Automation, and Nuclear Engineering
Imprint Place
Belgrade (Yugoslavia)
Imprint Pagination
8 p.
Report number
INIS-RS--0625

Conference

Title
Society for Electronics, Telecommunications, Automation, and Nuclear Engineering
Original Conference Title
ETAN'87: 31. Konferencija za elektroniku, telekomunikacije, automatiku i nuklearnu tehniku
Acronym
31. Conference - ETAN'87
Dates
1-5 Jun 1987
Place
Bled (Yugoslavia)

INIS

Country of Publication
Yugoslavia
Country of Input or Organization
Serbia
INIS RN
38015828
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BOUNDARY CONDITIONS; BOUNDARY ELEMENT METHOD; DIFFUSION EQUATIONS; DIRICHLET PROBLEM; FUEL RODS; HEAT FLUX; PWR TYPE REACTORS; SPATIAL DISTRIBUTION; TIME DEPENDENCE
Descriptors DEC
BOUNDARY-VALUE PROBLEMS; CALCULATION METHODS; DIFFERENTIAL EQUATIONS; DISTRIBUTION; ENRICHED URANIUM REACTORS; EQUATIONS; FINITE ELEMENT METHOD; FUEL ELEMENTS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
7 refs., 2 figs.