Thermal-mechanical coupling behavior analysis on metal-matrix dispersed plate-type fuel

被引:23
作者
Deng, Yangbin [1 ]
Wu, Yingwei [1 ]
Zhang, Dalin [1 ]
Lu, Qing [2 ]
Tian, Wenxi [1 ]
Qiu, Suizheng [1 ]
Su, G. H. [1 ]
机构
[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Shaanxi Key Lab Adv Nucl Energy & Technol, Xian 710049, Peoples R China
[2] Nucl Power Inst China, Key Lab Nucl Reactor Syst Design & Technol, Chengdu 610213, Peoples R China
基金
中国国家自然科学基金;
关键词
Dispersed plate-type fuel; Thermal-mechanical analysis; FROBA-PLATEs code; Bending and torsion; ANALYSIS CODE; EVOLUTION;
D O I
10.1016/j.pnucene.2016.11.007
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
In this study, according to the structure and material characteristics of the metal-matrix dispersed plate type fuel assembly, a series of mathematical and physical models were established, including thermal hydraulic analysis, stress-strain calculation, bending and torsion calculation and other auxiliary models. Based on these models, a thermal-mechanical coupling analysis scheme was designed and a fuel behavior analysis code FROBA-PLATEs was independently developed. The accuracy and reliability of the code FROBA-PLATEs was validated by the single-module validation method. The validated code was used to perform the thermal-mechanical behavior simulation of a hypothetical metal-matrix dispersed plate type fuel assembly. Significant parameters, such as flow distribution, temperature profile and stress strain profile, were obtained. In addition, some important thermal-mechanical phenomena, including the asymmetric heat transfer of the edge plate, the bending of side panel of and the torsion of the whole assembly, were simulated and evaluated. (C) 2016 Elsevier Ltd. All rights reserved.
引用
收藏
页码:8 / 22
页数:15
相关论文
共 21 条
[1]  
[Anonymous], 1873, TREATISE ELECT MAGNE
[2]   A NEW APPROACH TO THE APPLICATION OF MORI-TANAKA THEORY IN COMPOSITE-MATERIALS [J].
BENVENISTE, Y .
MECHANICS OF MATERIALS, 1987, 6 (02) :147-157
[3]  
Chao j, 1980, COBRA-3C/RERTR: A Thermal-hydraulic subchannel code with low pressure capabilities
[4]   CORRELATION FOR BOILING HEAT TRANSFER TO SATURATED FLUIDS IN CONVECTIVE FLOW [J].
CHEN, JC .
INDUSTRIAL & ENGINEERING CHEMISTRY PROCESS DESIGN AND DEVELOPMENT, 1966, 5 (03) :322-&
[5]   CONCEPTUAL DESIGN LOSS-OF-COOLANT ACCIDENT ANALYSIS FOR THE ADVANCED NEUTRON SOURCE REACTOR [J].
CHEN, NCJ ;
WENDEL, MW ;
YODER, GL .
NUCLEAR TECHNOLOGY, 1994, 105 (01) :104-122
[6]   Development of a thermal-mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs [J].
Deng, Yangbin ;
Wu, Yingwei ;
Zhang, Dalin ;
Tian, Wenxi ;
Qiu, Suizheng ;
Su, G. H. .
NUCLEAR ENGINEERING AND DESIGN, 2016, 301 :353-365
[7]  
Geelhood K. J., 2014, NUREGCR7024 PAC NW N
[8]   A new method to simulate the micro-thermo-mechanical behaviors evolution in dispersion nuclear fuel elements [J].
Gong, Xin ;
Zhao, Yunmei ;
Ding, Shurong .
MECHANICS OF MATERIALS, 2014, 77 :14-27
[9]  
James M.G., 2004, Mechanics of Materials, V6th
[10]   Development of thermal hydraulic and margin analysis code for steady state forced and natural convective cooling of plate type fuel research reactors [J].
Jo, Daeseong ;
Park, Jonghark ;
Chae, Heetaek .
PROGRESS IN NUCLEAR ENERGY, 2014, 71 :39-51