CFD CODE APPLICATION: CALCULATING HEAT TRANSFER IN A REACTOR WITH SUPERCRITICAL PARAMETERS

被引：0

作者：

Smirnov, V. P. ^{[1
]}

Papandin, M. V. ^{[1
]}

Loninov, A. Ya. ^{[1
]}

Vanyukova, G. V. ^{[1
]}

Afonin, S. Yu. ^{[1
]}

机构：

[1] Dollezhal Res & Dev Inst Power Engn NIKIET, Moscow, Russia

来源：

ATOMIC ENERGY | 2012年 / 111卷 / 04期

关键词：

Fuel Element; Fuel Assembly; Channel Calculation; Adjoint Problem; Maximum Surface Temperature;

D O I：

10.1007/s10512-012-9485-x

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Thermohydraulic calculations of isolated and communicating cells of a rod bundle were performed by the channel method for CANDU-X fuel assemblies and by a three-dimensional method. It was established that in solving the problem for the tightest cell in the case q = const the azimuthal nonuniformity of the temperature was found to decrease by 77 degrees C but it too was inadmissibly large. The temperature distribution along the surface of a fuel element in the case q = const was found to be different from the solution of the adjoint problem. A region with elevated coolant temperature, impeding heat exchange between two neighboring cells, was found between two adjoining cells. It was found that to evaluate computational reliability an experimental study must be performed on rod assemblies with supercritical coolant parameters.

引用

页码：252 / 259

页数：8

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