Local effect model development for the steam generator three dimensional thermal hydraulics analysis code

被引：12

作者：

Wang, Xi ^{[1
]}

Wang, Mingjun ^{[1
]}

Wu, Ge ^{[2
]}

Zhang, Jing ^{[1
]}

Qiu, Suizheng ^{[1
]}

Su, G. H. ^{[1
]}

Tian, Wenxi ^{[1
]}

机构：

[1] Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Shaanxi, Peoples R China

[2] Nucl Power Inst China, Chengdu, Sichuan, Peoples R China

来源：

ANNALS OF NUCLEAR ENERGY | 2020年 / 136卷

基金：

中国国家自然科学基金;

关键词：

Model development; Steam generator; Local effect; CFD; SECONDARY-SIDE; HEAT-TRANSFER; 2-PHASE FLOW; LEAKAGE;

D O I：

10.1016/j.anucene.2019.107020

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：

The thermal hydraulic characteristics of steam generator secondary side in pressurized water reactor has been always a research hot point in the literatures. The detailed three dimensional thermal hydraulic parameters distribution in steam generator is very important for the reactor safety and economy. A three-dimensional two-phase analysis program STAF for the secondary side of steam generator has been developed by NuTheL at Xi'an Jiaotong University. The program is based on porous medium model and four-equation drift flow model. It can simulate the flow and heat transfer characteristics of steam generator. However, due to the limitation of porous medium model, STAF are not functional to obtain the local velocity distribution near the supporting plate and anti-vibration bars, which are very important for fouling deposition and flow vibration analysis. In this paper, the local detailed thermal hydraulic characteristics near steam generator supporting plate and anti-vibration bars are studied. The local flow field is obtained and the influence range and degree of local components on the velocity distribution is analyzed. The supporting plate and anti-vibration bars analysis model was developed and implemented into the STAF code. Results show that the improved code could predict the local velocity variations compared with the original code. This work is meaningful for the function promotion of steam generator thermal hydraulic code STAF. (C) 2019 Elsevier Ltd. All rights reserved.

引用

页数：9

共 26 条

[1]

[Anonymous], 1998, VALIDATION THIRST ST

[2]

[Anonymous], 1984, ATHOS COMPUTER PROGR

[3]

[Anonymous], MECH MODEL PREDICTIN

[4]

Carver M.B., 1981, Thermal-Hydraulics in Recirculating Steam Generators - THIRST Code User's Manual

[5]

Cizelj L., 1995, 2nd Regional Meeting: Nuclear Energy in Central Europe. Annual Meeting of the Nuclear Society of Slovenia Proceedings, P276

[6] Study on secondary side flow of steam generator with coupled heat transfer from primary to secondary side [J].

Cong, Tenglong ;

Tian, Wenxi ;

Qiu, Suizheng ;

Su, Guanghui .

APPLIED THERMAL ENGINEERING, 2013, 61 (02) :519-530

[7] Three-dimensional study on steady thermohydraulics characteristics in secondary side of steam generator [J].

Cong, Tenglong ;

Tian, Wenxi ;

Su, Guanghui ;

Qiu, Suizheng ;

Xie, Yongcheng ;

Yao, Yangui .

PROGRESS IN NUCLEAR ENERGY, 2014, 70 :188-198

[8]

Fang D., PROG NUCL ENERGY, V118

[9] Numerical investigation of thermal-hydraulic characteristics in a steam generator using a coupled primary and secondary side heat transfer model [J].

Li, Yanjun ;

Yang, Yuanlong ;

Sun, Baozhi .

ANNALS OF NUCLEAR ENERGY, 2013, 55 :258-264

[10]

Mohany A., 2009, Flow-induced vibration and fretting-wear performance of candu steam generator u-tubes: Instrumentation

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