TRACE qualification via analysis of the EIR gas-loop experiments with smooth rods

被引：17
作者：
Epiney, Aaron [1 ,2 ]
Mikityuk, Konstantin [1 ]
Chawla, Rakesh [1 ,2 ]
机构：
[1] Paul Scherrer Inst, CH-5232 Villigen, Switzerland
[2] Ecole Polytech Fed Lausanne, CH-1015 Lausanne, Switzerland
来源：
ANNALS OF NUCLEAR ENERGY | 2010年 / 37卷 / 06期
关键词：
Heat exchange; Friction; TRACE; Gas-loop experiments; HEAT-TRANSFER; PRESSURE-DROP; FLOW; BUNDLES; REACTOR; PIPE;
D O I：
10.1016/j.anucene.2010.01.020
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：
Several gas-loop experimental programs were carried out during the 1970-1980s at the Eidgenossisches Institut fur Reaktorforschung (EIR, now PSI), Switzerland. In the present work, a wide range of thermalhydraulics tests for smooth rods, which form part of the experiments conducted at the time, have been reanalyzed with the aim of qualifying the TRACE code. The latter constitutes the thermal-hydraulics module of PSI's FAST code system, currently being applied to the multi-physics analysis of advanced fast reactor systems, including the Generation IV Gas-Cooled Fast Reactor (GFR). It is shown, from the present analysis, that the built-in TRACE heat transfer and friction correlations are indeed quite suitable for gas cooling under prototypic GFR conditions. (C) 2010 Elsevier Ltd. All rights reserved.
引用
收藏
页码：875 / 887
页数：13
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