Thermal-hydraulic analysis for a sodium-heated steam generator using a multi-shell method

被引：5
|
作者：
Sakai, T
Yamaguchi, A
Metz, P
机构：
[1] Japan Nuc Cycle Dev Inst, Oorai Engn Ctr, Thermal Hydraul Res Grp, Oarai, Ibaraki 3111393, Japan
[2] Japan Nucl Cycle Dev Inst, Int Cooperat & Technol Dev Ctr, Syst Engn Grp, Tsuruga, Fukui 9191279, Japan
来源：
NUCLEAR ENGINEERING AND DESIGN | 2003年 / 219卷 / 01期
关键词：
Heat transfer - Hydraulics - Liquid metal cooled reactors - Nuclear power plants - Thermal effects;
D O I：
10.1016/S0029-5493(02)00212-1
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：
A multi-shell analysis method has been applied to predict the Thermal-hydraulics in a steam generator of a liquid metal reactor. The method is intended to improve the calculation accuracy for temperature profiles at a wide range of heat exchange rates in a large sized steam generator for the future plant. The calculation accuracy has been examined using experimental 50 MWth steam generator test data that were measured during 1970's-1980's. The calculation results of temperature profiles were compared with experimental data at 20, 30, 50, 75, 90, and 100% of nominal operating condition. Responses for the stepwise flow rate variations were also evaluated. In conclusion, the calculation accuracy for the temperature profile in the steam generator was improved by using the multi-shell analysis method for a wide range of heat exchange rates. (C) 2002 Elsevier Science B.V. All rights reserved.
引用
收藏
页码：35 / 46
页数：12
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