Three-dimensional numerical simulation of flow and heat transport in high-temperature nuclear reactors

被引：0

作者：

Becker, S ^{[1
]}

Laurien, E ^{[1
]}

机构：

[1] Univ Stuttgart, Inst Nucl Technol & Energy Syst, IKE, D-70550 Stuttgart, Germany

来源：

HIGH PERFORMANCE COMPUTING IN SCIENCE AND ENGINEERING '02 | 2003年

关键词：

D O I：

暂无

中图分类号：

TP301 [理论、方法];

学科分类号：

081202 ;

摘要：

In next generation nuclear High-Temperature Reactors an annular nuclear core consisting of a central column of graphite spheres and a surrounding ring of fuel pebbles is employed. Due to the complex feeding and shutdown mechanisms three-dimensional effects of heat production, gas flow and heat transport may become important for safety analysis. To simulate flow and heat transport in the core and the surrounding graphite reflector a new code system based on CFX-4 has been developed and run on the NEC-SX4 and NEC-SX5 supercomputers. The simulations are performed with the Heterogeneous Model of porous media. The program has been verified by comparison with two-dimensional simulations of the HTR-MODUL using the well established thermal analysis code THERMIX. A sensitivity study of several models for pressure drop and heat transfer on a simplified model of an HTR-MODUL is performed. Additionally the influence of the variation of the volume porosity near walls on flow and heat transport is analysed. In order to demonstrate the simulation of three-dimensional effects the influence of a package of fuel pebbles located asymmetrically in the central column is investigated. A significant influence on the temperature distribution and the maximum temperature core is found.

引用

页码：367 / 378

页数：12

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