基于有限元方法的惰性基弥散燃料传热性能研究

doi:10.11889/j.0253-3219.2018.hjs.41.090604

Nuclear Techniques ›› 2018, Vol. 41 ›› Issue (9): 90604-090604.doi: 10.11889/j.0253-3219.2018.hjs.41.090604

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles

Heat transfer performance of inert matrix dispersion pellet based on finite element analysis

LU Zhiwei, ZHANG Yongdong, LI Lei, LIU Tong, XUE Jiaxiang

Nuclear Fuel Research and Development Center, Department of ATF R & D, Shenzhen 518026, China

Received:2017-10-26 Revised:2018-05-16 Online:2018-09-10 Published:2018-09-12
Supported by:
Supported by National Major Special Projects (No.2015ZX06004-001)

Abstract

Abstract: [Background] 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 UO₂.[Purpose] 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] A FEA model is developed by ABAQUS combined its secondary development function.[Results] 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 UO₂. When the thermal barrier between TRISO and matrix increases from 0 to 4×10^-4 m²·℃·W^-1, the ETC of IMDP decreases approximately 16% and 19% respectively at beginning of life (BOL) and middle of life (MOL).[Conclusions] IMDP has superior heat transfer performance than UO₂. Thermal barrier between TRISO and matrix has more significant impact on BOL IMDP than MOL IMDP. Thermal barrier between 0 to 4×10^-4 m²·℃·W^-1 has more significant impact on ETC of IMDP than other values.

Key words: Accident tolerant, Inert matrix, Nuclear fuel, Heat transfer

CLC Number:

TL33

LU Zhiwei, ZHANG Yongdong, LI Lei, LIU Tong, XUE Jiaxiang. Heat transfer performance of inert matrix dispersion pellet based on finite element analysis[J].Nuclear Techniques, 2018, 41(9): 90604-090604.

References

1 Zinkle S J, Terrani K A, Gehin J C, et al. Accident tolerant fuels for LWRs:a perspective[J]. Journal of Nuclear Materials, 2014, 448(1-3):374-379. DOI:10.1016/j. jnucmat.2013.12.005.
2 Lee Y, Cho N Z. Three-dimensional single-channel thermal analysis of fully ceramic microencapsulated fuel via two-temperature homogenized model[J]. Annals of Nuclear Energy, 2014, 71:254-271. DOI:10.1016/j. anucene.2014.03.039.
3 Lee Y, Cho N Z. Steady and transient state analyses of fully ceramic microencapsulated fuel loaded reactor core via two-temperature homogenized thermal conductivity model[J]. Annals of Nuclear Energy, 2015, 76:283-296. DOI:10.1016/j.anucene.2014.09.027.
4 Wu X L, Li W, Wang Y, et al. Preliminary safety analysis of the PWR with accident tolerant fuels during severe accident conditions[J]. Annals of Nuclear Energy, 2015, 80:1-13. DOI:10.1016/j.anucene.2015.02.040.
5 Lee H G, Kim D, Lee S J, et al. Thermal conductivity analysis of SiC ceramics and fully ceramic microencapsulated fuel composites[J]. Nuclear Engineering and Design, 2017, 311:9-15. DOI:10.1016/j. nucengdes.2016.11.005.
6 Kou H S, Lu K T, Yu C C. Effective thermal conductivity of composite material with spherical inclusions in orthorhombic structure[J]. Computer & Structures, 1994, 53(3):569-577.
7 Maxwell J C. A treatise on electricity and magnetism[M]. Cambridge:Cambridge University Press, 2010:111.
8 Carson J K, Lovatt S J, Tanner D J, et al. Thermal conductivity bounds for isotropic, porous materials[J]. International Journal of Heat and Mass Transfer, 2005, 48(11):2150-2158. DOI:10.1016/j.ijheatmasstransfer. 2004.12.032.
9 Gonzo E E. Estimating correlations for the effective thermal conductivity of granular materials[J]. Chemical Engineering Journal, 2002, 90(3):299-302. DOI:10.1016/S1385-8947(02)00121-3.
10 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.
11 Terrani K A, Snead L L, Gehin J C. Microencapsulated fuel technology for commercial light water and advanced reactor application[J]. Journal of Nuclear Materials, 2012, 427(1-3):209-224. DOI:10.1016/j.jnucmat.2012.05.021.
12 Powers J J. Fully ceramic microencapsulated (FCM) replacement fuel for LWRs (TM-2013/173)[R]. USA:Oak Ridge National Laboratory, 2013.
13 Cheon J S, Lee B H, Koo Y H, et al. Evaluation of a pellet-clad mechanical interaction in mixed oxide fuels during power transients by using axisymmetric finite element modeling[J]. Nuclear Engineering and Design, 2004, 231(1):39-50. DOI:10.1016/j.nucengdes.2004. 02.009.
14 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.

[1]	Yushuang CHEN, Jian TIAN, Haihua ZHU, Yuan FU, Naxiu WANG. Experimental study on turbulent convective heat transfer of molten salts in circular tubes [J]. Nuclear Science and Techniques, 2019, 42(4): 40601-040601.
[2]	HU Jian, SHI Xingwei, LEI Lei, XU Chao, WEN Lijing, QIAO Xuedong. Assessment of heat transfer phenomenon scaling distortion in CERT [J]. Nuclear Techniques, 2018, 41(3): 30602-030602.
[3]	MIAO Hongkang, CHEN Yushuang, LYU Liushuai, WANG Naxiu. Numerical simulation study on heat transfer characteristics of new heat exchange fins [J]. Nuclear Techniques, 2018, 41(10): 100601-100601.
[4]	FAN Qiwei, ZHU Haihua, CHEN Yushuang, WANG Naxiu, ZHU Zhiyuan. Heat transfer characteristics of molten salt in finned tube [J]. Nuclear Techniques, 2017, 40(7): 70602-070602.
[5]	WANG Dejun, HE Miao, QIN Zhi, HUANG Qing, DU Shiyu. Current status of studies on point defect structures of uranium carbide nuclear fuels [J]. Nuclear Techniques, 2017, 40(7): 70606-070606.
[6]	JING Jianping, JIA Bin, LEI Lei, BI Jinsheng, ZUO Jiaxu, LIU Yaning, ZHANG Chunming, ZHANG Dalin. Characteristic of core flow and heat transfer of different fuel ball arrangement modes in molten salt reactor [J]. Nuclear Techniques, 2017, 40(2): 20602-020602.
[7]	HE Peifeng, XU Bin, LUO Ying, YU Hao, MA Ziqi, SUN Shanwen, ZHOU Jinxiong. Numerical simulation on the convective heat transfer of compressive gas in ACP100 integrated head package [J]. Nuclear Techniques, 2016, 39(10): 100601-100601.
[8]	XU Yongjian, LI Xiang, HU Chundong, YU Ling, TAO Ling, XIE Yahong, JIANG Caichao, GU Yuming, LI Jun. Analysis of heat transfer capacity of electron dump on EAST-NBI [J]. Nuclear Techniques, 2016, 39(10): 100602-100602.
[9]	GE Zhihao, PENG Yongsheng, LYU Yijun, DENG Weiping, ZHAO Pinghui. Turbulent heat transfer of liquid metal inside the sub-channels of reactor core [J]. Nuclear Techniques, 2015, 38(9): 90603-090603.
[10]	ZHOU Jinhao, SUN Bo, SHE Changfeng, DOU Qiang, LONG Dewu, LI Qingnuan, WU Guozhong. Experimental research on the formation and controlling of molten salt frozen-wall [J]. Nuclear Techniques, 2015, 38(7): 70602-070602.
[11]	TIAN Jin, XIA Xiaobin, PENG Chao, ZHANG Zhihong. Impact analysis of criticality safety for 10-MWt solid thorium-based molten salt reactor spent nuclear fuel storage system [J]. Nuclear Techniques, 2015, 38(5): 50602-050602.
[12]	MAI Xiyuan, ZHANG Feng, LIN Jun, WANG Peng, ZHU Zhiyong. Hydrodynamics of spouted bed in TRISO particle buffer layer coating process [J]. Nuclear Techniques, 2015, 38(4): 40501-040501.
[13]	SUN Bo, ZHOU Jinhao, SHE Changfeng, LONG Dewu, DOU Qiang, HU Weiqing, LI Qingnuan. Heat transfer characteristics of high-temperature [J]. Nuclear Techniques, 2015, 38(3): 30601-030601.
[14]	SONG Mingqiang, ZHOU Tao, CHEN Baixu, HUANG Yanping, XIA Bangyang. Heat transfer characteristics of supercritical water in different shape channels [J]. Nuclear Techniques, 2015, 38(10): 100603-100603.
[15]	LIN Chao, CAI Chuangxiong, WANG Kai, HE Zhaozhong, CHEN Kun. Performance analysis of the air cooling tower for nitrate natural circulation loop [J]. Nuclear Techniques, 2014, 37(12): 120601-120601.

Heat transfer performance of inert matrix dispersion pellet based on finite element analysis

PDF (PC)

Like

Knowledge

Abstract

Cite this article

share this article

References

Related Articles 15

Metrics

Comments

Recommended 10