Thermal-hydraulic modeling and transient analysis of pressurized water reactors

被引：1
|
作者：
Han, GY
Stanley, TP
Secker, PA
机构：
[1] Korea Atom Energy Res Inst, Taejon 305353, South Korea
[2] Univ Arizona, Dept Nucl Engn, Tucson, AZ 85721 USA
来源：
INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER | 1999年 / 26卷 / 07期
关键词：
D O I：
10.1016/S0735-1933(99)00080-9
中图分类号：
O414.1 [热力学];
学科分类号：
摘要：
This paper examines a new dynamic moving boundary thermal-hydraulic fuel pin model (FUELPIN) for the transient analysis of a pressurized water reactor (PWR). FUELPIN is developed to accommodate the reactor core thermal-hydraulic model of the fuel pin and adjacent coolant flow channel, with detailed thermal conduction in fuel elements. Transient analyses using a known thermal-hydraulic analysis code, COBRA, and FUELPIN linked with a PWR system analysis code show that the thermal margin gains more by a transient MDNBR approach than the traditional quasi-steady methodology for a PWR. The studies of the nuclear reactor system show that moving boundary formulation is highly suitable for the transient thermal-hydraulic analysis of PWRs. (C) 1999 Elsevier Science Ltd.
引用
收藏
页码：909 / 918
页数：10
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