Sensitivity study for accident tolerant fuels: Property comparisons and behavior simulations in a simplified PWR to enable ATF development and design

被引:23
作者
Spencer, Kristina Yancey [1 ]
Sudderth, Laura [1 ,2 ]
Brito, Ryan A. [1 ]
Evans, Jordan A. [1 ]
Hart, Clifford S. [1 ]
Hu, Anbang [1 ]
Jati, Andi [1 ]
Stern, Karyn [1 ]
McDeavitt, Sean M. [1 ]
机构
[1] Texas A&M Univ, TAMU 3133, College Stn, TX 77843 USA
[2] Idaho Natl Lab, 2525 Fremont Ave, Idaho Falls, ID 83415 USA
关键词
ENHANCED THERMAL-CONDUCTIVITY; URANIUM NITRIDE FUEL; MECHANICAL-PROPERTIES; BERYLLIUM-OXIDE; SILICON-CARBIDE; COMPOSITE FUEL; MONONITRIDE; PERFORMANCE; DIOXIDE; UN;
D O I
10.1016/j.nucengdes.2016.09.009
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
Since the events at the Fukushima-Daiichi nuclear power plant, there has been increased interest in developing fuels to better withstand accidents for current light water reactors. Four accident tolerant fuel candidates are uranium oxide with beryllium oxide additives, uranium oxide with silicon carbide matrix additives, uranium nitride, and uranium nitride with uranium silicide composite. The first two candidates represent near-term high performance uranium oxide with high thermal conductivity and neutron transparency, and the second two represent mid-term high-density fuels with highly beneficial thermal properties. This study seeks to understand the benefits and drawbacks of each option in place of uranium dioxide. To assess the material properties for each of the fuel types, an extensive literature review was performed for material property data. Correlations were then made to evaluate the properties during reactor operation. Neutronics and thermal hydraulics studies were also completed to determine the impact of the use of each candidate in an AP1000 reactor. In most cases, the candidate fuels performed more desirably than uranium dioxide, but no fuel type performed better in all aspects. Much more research needs to be performed to build a complete model of the fuel performances, primarily experimental data for uranium silicide. Each of the fuels studied has its own benefits and drawbacks, and the comparisons discussed in this report can be used to aid in determining the most appropriate fuel depending on the desired specifications. (C) 2016 Elsevier B.V. All rights reserved.
引用
收藏
页码:197 / 212
页数:16
相关论文
共 52 条
[1]  
Ainscough J., 1982, GAP CONDUCTION ZIRCA
[2]  
[Anonymous], 2008, THERMOPHYSICAL PROPE
[3]  
[Anonymous], 1996, Fundamentals of Heat and Mass Transfer
[4]  
[Anonymous], 2014, NIST Chemistry Webbook
[5]   THE EFFECT OF OXYGEN IMPURITY ON THE CHARACTERISTICS OF URANIUM AND URANIUM PLUTONIUM MIXED NITRIDE FUELS [J].
ARAI, Y ;
MORIHIRA, M ;
OHMICHI, T .
JOURNAL OF NUCLEAR MATERIALS, 1993, 202 (1-2) :70-78
[6]   FABRICATION AND PROPERTIES OF DENSE BERYLLIUM OXIDE [J].
CARNIGLIA, SC ;
HOVE, JE .
JOURNAL OF NUCLEAR MATERIALS, 1961, 4 (02) :165-176
[7]   Coupled analysis for new fuel design using UN and UC for SCWR [J].
Chaudri, Khurrum Saleem ;
Tian, Wenxi ;
Su, Yali ;
Zhao, Hao ;
Zhu, Dahuan ;
Su, Guanghui ;
Qiu, Suizheng .
PROGRESS IN NUCLEAR ENERGY, 2013, 63 :57-65
[8]  
Chicot D., 2010, CERAM MAT, P978
[9]   MICROHARDNESS OF SINGLE CRYSTALS OF BEO AND OTHER WURTZITE COMPOUNDS [J].
CLINE, CF ;
KAHN, JS .
JOURNAL OF THE ELECTROCHEMICAL SOCIETY, 1963, 110 (07) :773-775
[10]  
Curkovic L, 2010, KEM IND, V59, P483