
浏览全部资源
扫码关注微信
中广核研究院有限公司 事故容错燃料研发项目部 深圳 518026
[ "卢志威, 男, 1985年出生, 2011年于西安交通大学获硕士学位, 研究领域为核燃料设计", "LU Zhiwei, male, born in 1985, graduated from Xi'an Jiao Tong University with a master's degree in 2011, focusing on nuclear fuel design" ]
刘彤, E-mail:liutong@cgnpc.com.cn LIU Tong, E-mail:liutong@cgnpc.com.cn
收稿日期:2017-10-26,
修回日期:2018-05-16,
纸质出版日期:2018-09
移动端阅览
卢志威, 张永栋, 李雷, 等. 基于有限元方法的惰性基弥散燃料传热性能研究[J]. 核技术, 2018,41(9):090604
Zhiwei LU, Yongdong ZHANG, Lei LI, et al. Heat transfer performance of inert matrix dispersion pellet based on finite element analysis[J]. Nuclear techniques, 2018, 41(9): 090604
卢志威, 张永栋, 李雷, 等. 基于有限元方法的惰性基弥散燃料传热性能研究[J]. 核技术, 2018,41(9):090604 DOI: 10.11889/j.0253-3219.2018.hjs.41.090604.
Zhiwei LU, Yongdong ZHANG, Lei LI, et al. Heat transfer performance of inert matrix dispersion pellet based on finite element analysis[J]. Nuclear techniques, 2018, 41(9): 090604 DOI: 10.11889/j.0253-3219.2018.hjs.41.090604.
惰性基弥散燃料芯块(Inert Matrix Dispersion Pellet,IMDP)以高温气冷堆燃料技术为基础,采用惰性材料作为三重各向同性型(Tristructural Isotropic,TRISO)燃料颗粒的弥散基体,相比传统的UO
2
燃料,其最典型特征是具备高热导率。采用通用有限元软件ABAQUS,结合其二次开发功能,建立有限元计算模型,研究了温度、燃耗以及燃料颗粒与惰性基体间热阻对IMDP燃料有效热导率影响规律,并与UO
2
陶瓷燃料进行对比。结果表明:IMDP有效热导率随燃耗及温度的增加而减小,且在不同寿期及不同温度下,IMDP有效热导率均明显高于UO
2
热导率;反应堆正常运行工况下,相比UO
2
芯块,IMDP较高的热导率会使芯块中心温度显著降低;此外,燃料颗粒与惰性基体间热阻在0~4×10
-4
m
2
·℃·W
-1
范围内对IMDP的有效热导率影响程度最为敏感。
Background
2
Inert matrix dispersion pellet (IMDP)
based on the fuel technology of high temperature gas cooled reactor
a type of accident tolerant fuel
takes inert material as matrix
has high thermal conductivity compared to UO
2
.
Purpose
2
In this study
effect of temperature
burnup
thermal barrier between tristructural isotropic (TRISO) and matrix on the effective thermal conductivity (ETC) of the IMDP is studied by finite element analysis (FEA) method.
Methods
2
A FEA model is developed by ABAQUS combined its secondary development function.
Results
2
The ETC of IMDP decreases as temperature and burnup increases. Under normal operation condition
the centerline temperature of IMDP is 400℃ or more lower than UO
2
. When the thermal barrier between TRISO and matrix increases from 0 to 4×10
-4
m
2
·℃·W
-1
the ETC of IMDP decreases approximately 16% and 19% respectively at beginning of life (BOL) and middle of life (MOL).
Conclusions
2
IMDP has superior heat transfer performance than UO
2
. Thermal barrier between TRISO and matrix has more significant impact on BOL IMDP than MOL IMDP. Thermal barrier between 0 to 4×10
-4
m
2
·℃·W
-1
has more significant impact on ETC of IMDP than other values.
S J Zinkle , K A Terrani , J C Gehin , . Accident tolerant fuels for LWRs:a perspective . Journal of Nuclear Materials , 2014 . 448 ( 1-3 ): 374 - 379 . DOI: 10.1016/j.jnucmat.2013.12.005 http://doi.org/10.1016/j.jnucmat.2013.12.005 .
Y Lee , N Z Cho . Three-dimensional single-channel thermal analysis of fully ceramic microencapsulated fuel via two-temperature homogenized model . Annals of Nuclear Energy , 2014 . 71 254 - 271 . DOI: 10.1016/j.anucene.2014.03.039 http://doi.org/10.1016/j.anucene.2014.03.039 .
Y Lee , N Z Cho . Steady and transient state analyses of fully ceramic microencapsulated fuel loaded reactor core via two-temperature homogenized thermal conductivity model . Annals of Nuclear Energy , 2015 . 76 283 - 296 . DOI: 10.1016/j.anucene.2014.09.027 http://doi.org/10.1016/j.anucene.2014.09.027 .
X L Wu , W Li , Y Wang , . Preliminary safety analysis of the PWR with accident tolerant fuels during severe accident conditions . Annals of Nuclear Energy , 2015 . 80 1 - 13 . DOI: 10.1016/j.anucene.2015.02.040 http://doi.org/10.1016/j.anucene.2015.02.040 .
H G Lee , D Kim , S J Lee , . Thermal conductivity analysis of SiC ceramics and fully ceramic microencapsulated fuel composites . Nuclear Engineering and Design , 2017 . 311 9 - 15 . DOI: 10.1016/j.nucengdes.2016.11.005 http://doi.org/10.1016/j.nucengdes.2016.11.005 .
H S Kou , K T Lu , C C Yu . Effective thermal conductivity of composite material with spherical inclusions in orthorhombic structure . Computer & Structures , 1994 . 53 ( 3 ): 569 - 577 . http://cn.bing.com/academic/profile?id=ad1a9ec452994e611045ea82279d13b0&encoded=0&v=paper_preview&mkt=zh-cn .
J C Maxwell . A treatise on electricity and magnetism , : Cambridge Cambridge University Press , 2010 . 111 .
J K Carson , S J Lovatt , D J Tanner , . Thermal conductivity bounds for isotropic, porous materials . International Journal of Heat and Mass Transfer , 2005 . 48 ( 11 ): 2150 - 2158 . DOI: 10.1016/j.ijheatmasstransfer.2004.12.032 http://doi.org/10.1016/j.ijheatmasstransfer.2004.12.032 .
E E Gonzo . Estimating correlations for the effective thermal conductivity of granular materials . Chemical Engineering Journal , 2002 . 90 ( 3 ): 299 - 302 . DOI: 10.1016/S1385-8947(02)00121-3 http://doi.org/10.1016/S1385-8947(02)00121-3 .
Stainsby R, Grief A, Worsley M, et al . Investigation of local heat transfer phenomena in a pebble bed HTGR core (NR001/RP/002R01)[R]. United Kingdom: Amec Foster Wheeler-Nuclear, 2009.
K A Terrani , L L Snead , J C Gehin . Microencapsulated fuel technology for commercial light water and advanced reactor application . Journal of Nuclear Materials , 2012 . 427 ( 1-3 ): 209 - 224 . DOI: 10.1016/j.jnucmat.2012.05.021 http://doi.org/10.1016/j.jnucmat.2012.05.021 .
Powers J J. Fully ceramic microencapsulated (FCM) replacement fuel for LWRs (TM-2013/173)[R]. USA: Oak Ridge National Laboratory, 2013.
J S Cheon , B H Lee , Y H Koo , . Evaluation of a pellet-clad mechanical interaction in mixed oxide fuels during power transients by using axisymmetric finite element modeling . Nuclear Engineering and Design , 2004 . 231 ( 1 ): 39 - 50 . DOI: 10.1016/j.nucengdes.2004.02.009 http://doi.org/10.1016/j.nucengdes.2004.02.009 .
MacDonald P E, Thompson L B. MATPRO: a handbook of materials properties for use in the analysis of light water reactor fuel rod behavior[R]. Version 09. USA: Idaho National Engineering Laboratory, 1976.
0
浏览量
25
下载量
0
CSCD
关联资源
相关文章
相关作者
相关机构
京公网安备11010802024621