NDLI: Study on Temperature Distribution of Pebble-Bed HTR Fuel Element by Using Boundary Element Method

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Study on Temperature Distribution of Pebble-Bed HTR Fuel Element by Using Boundary Element Method

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Study on Temperature Distribution of Pebble-Bed HTR Fuel Element by Using Boundary Element Method

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Wang, Haitao Wang, Xin
Copyright Year	2013
Abstract	Spherical fuel elements with a diameter of 60mm are basic units of the nuclear fuel for the pebble-bed high temperature gas-cooled reactor (HTR). Each fuel element is treated as a graphite matrix containing around 10,000 randomly distributed fuel particles. The essential safety concept of the pebble-bed HTR is based on the objective that maximum temperature of the fuel particles does not exceed the design value. In this paper, a microstructure-based boundary element model is proposed for the large-scale thermal analysis of a spherical fuel element. This model presents detailed structural information of a large number of coated fuel particles dispersed in a spherical graphite matrix in order that temperature distributions at the level of fuel particles can be evaluated. The model is meshed with boundary elements in conjunction with the fast multipole method (FMM) in order that such large-scale computation is performed only in a personal desktop computer. Taking advantage of the fact that fuel particles are of the same shape, a similar sub-domain approach is used to establish the temperature translation mechanism between various layers of each fuel particle and to simplify the associated boundary element formulation. The numerical results demonstrate large-scale capacity of the proposed method for the multi-level temperature evaluation of the pebble-bed HTR fuel elements.
Sponsorship	Pressure Vessels and Piping Division Nondestructive Evaluation Engineering Division
File Format	PDF
ISBN	9780791855713
DOI	10.1115/PVP2013-97454
Volume Number	Volume 6B: Materials and Fabrication
Conference Proceedings	ASME 2013 Pressure Vessels and Piping Conference
Language	English
Publisher Date	2013-07-14
Publisher Place	Paris, France
Access Restriction	Subscribed
Subject Keyword	Computers Temperature distribution Temperature Boundary element methods Fuels Design Nuclear fuels Very high temperature reactors Computation Particulate matter Graphite Safety Shapes Thermal analysis
Content Type	Text
Resource Type	Article

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