Preliminary evaluation of U3Si2-FeCrAl fuel performance in light water reactors through a multi-physics coupled way

被引:50
作者
He, Yanan [1 ]
Chen, Ping [1 ,2 ]
Wu, Yingwei [1 ]
Su, G. H. [1 ]
Tian, Wenxi [1 ]
Qiu, Suizheng [1 ]
机构
[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Shaanxi Engn Res Ctr Adv Nucl Energy, Xian 710049, Shaanxi, Peoples R China
[2] Nucl Power Inst China, Sci & Technol Reactor Syst Design Technol Lab, Chengdu 610213, Sichuan, Peoples R China
基金
中国国家自然科学基金;
关键词
U3Si2; Multiphysics; Fuel performance; MOOSE; BEEs; ACCIDENT-TOLERANT FUELS; NORMAL OPERATION; CREEP;
D O I
10.1016/j.nucengdes.2017.12.019
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
U3Si2-FeCrAl fuel system is a potential choice for Accident Tolerant Fuel (ATF) for its higher uranium density, improved fuel thermal conductivity and stronger oxidation resistance. In this work, a new multi-physic fuel performance code called BEEs for LWR fuels has been developed based on Multiphysics Object-Oriented Simulation Environment (MOOSE) using the Object-Oriented Programming (OOP) method. As a first step to verify the capability of BEEs, one problem has been conducted using BEEs and compared with the results from BISON and ABAQUS. Then, the most recently available U3Si2-FeCrAl behavior models have been coded in BEEs. Fuel performance analysis was conducted for U3Si2-FeCrAl fuel system using BEEs and comparisons with UO2-Zr-4 and U3Si2-Zr-4 were made in this work. The results show that U3Si2-FeCrAl fuel system can lower the fuel peaking temperature about 300 K and have flat radial temperature distribution which can mitigate or eliminate the fuel cracking during power up. Further, the pellet-cladding mechanic interaction can be delayed or fully eliminated employing U3Si2-FeCrAl fuel system in light water reactors (LWRs).
引用
收藏
页码:27 / 35
页数:9
相关论文
共 25 条
[1]   An efficient model for the analysis of fission gas release [J].
Bernard, LC ;
Jacoud, JL ;
Vesco, P .
JOURNAL OF NUCLEAR MATERIALS, 2002, 302 (2-3) :125-134
[2]   Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U3Si2-FeCrAl [J].
Chen, Shengli ;
Yuan, Cenxi .
SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2017, 2017
[3]   Mechanism study and theoretical simulation on heat split phenomenon in dual-cooled annular fuel element [J].
Deng, Yangbin ;
Wu, Yingwei ;
Li, Yuanming ;
Zhang, Dalin ;
Tian, Wenxi ;
Su, G. H. ;
Qiu, Suizheng .
ANNALS OF NUCLEAR ENERGY, 2016, 94 :44-54
[4]   Creep behavior of commercial FeCrAl foils: Beneficial and detrimental effects of oxidation [J].
Dryepondt, Sebastien ;
Pint, Bruce A. ;
Lara-Curzio, Edgar .
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2012, 550 :10-18
[5]  
Gamble K., 2015, MULTISCALE MULTIPHYS
[6]   MOOSE: A parallel computational framework for coupled systems of nonlinear equations [J].
Gaston, Derek ;
Newman, Chris ;
Hansen, Glen ;
Lebrun-Grandie, Damien .
NUCLEAR ENGINEERING AND DESIGN, 2009, 239 (10) :1768-1778
[7]  
Geelhood K., 2011, FRAPCON 3 4 COMPUTER
[8]  
Hales J.D., 2013, Bison theory manual the equations behind nuclear fuel analysis
[9]   Creep of zirconium and zirconium alloys [J].
Hayes, Troy A. ;
Kassner, Michael E. .
METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 2006, 37A (08) :2389-2396
[10]   THE RADIAL-DISTRIBUTION OF PLUTONIUM IN HIGH BURNUP UO2 FUELS [J].
LASSMANN, K ;
OCARROLL, C ;
VANDELAAR, J ;
WALKER, CT .
JOURNAL OF NUCLEAR MATERIALS, 1994, 208 (03) :223-231