事故容错热导率增强型UO<sub>2</sub>核燃料的研究进展

doi:10.11896/cldb.18050107

Abstract
Figure/Table
References
Related Citation (2)

Download:

Full Text ( PDF ) (2662KB)
Export: BibTeX | EndNote (RIS)

Abstract The UO₂+Zr alloy fuel assembly is the most widely used nuclear fuel system for the current light water nuclear reactor. However, the Fukushima Daiichi nuclear disaster revealed the primary safety risks of UO₂+Zr alloy fuel system under accident, thereby various international programs have been launched to develop accident tolerant fuel (ATF). ATF is a new generation of fuel system developed to enhance the ability of nuclear fuel assembly under severe accident. The primary domain research of accident tolerant fuel is to design and improve current nuclear fuel forms and develop enhanced thermal conductivity UO₂ nuclear fuel on the basis of little change in industry. At present, the candidate fuel systems for thermal conductivity enhanced UO₂ that have achieved progress are the UO₂-SiC, UO₂-BeO, UO₂-diamond and UO₂-Mo. For the UO₂-SiC and UO₂-diamond systems, the details of the interfacial reactions between SiC/diamond and UO₂ have been poorly understood. The role of the evolution of properties for SiC and diamond on the thermos-physical performance of UO₂ under irradiation has yet to be fully defined. Nevertheless, electric field assisted sintering (FAST) technology is an effective method to suppress the interfacial reaction and fabricate UO₂-SiC and UO₂-diamond. In the UO₂-BeO system, the excellent chemical compatibility between BeO and UO₂, and the enhancement effect for thermal conductivity of UO₂ has been demonstrated through the extensive work. Accordingly, UO₂-BeO is regarded as the candidate fuel system for industrial application. However, the Be presenting as the scarcity material for the strategic resource, and the toxic nature of BeO as well as the transformation of spent fuel reprocessing processes, should be considered for industrialization. In the UO₂-Mo system, Mo has been considered as the most potential additive among the metals, and indicates outstanding thermal conductivity enhancement for the three-dimensional network distribution. Moreover, such microstructure is beneficial for retaining fission products. Compared with other additives, Mo has the property of higher neutron absorption cross section, and thus the amount of addition should be reasonably regulated. While such fuel system also should be investigated in detail. It is well accepted that the candidate fuel system above is still lacks of irradiation data for assessments. High-throughput preparation and machine learning could be introduced into the development of thermal conductivity enhanced UO₂ to accomplish the industrial application at an earlier time. This review offers a retrospection of the research efforts with respect to the thermal conductivity enhanced UO₂, and provides the fabrication process, microstructure and thermal conductivity respectively. Then the current problems confronting the thermal conductivity enhanced UO₂ are concerned as well as the application prospects are presented to the benefit for ATF in light water reactor.

Key words： light water reactor accident tolerant fuel uranium dioxide second phase

Published: 21 May 2019

CLC number:

TB321

Fund:This work was financially supported by National Key Research and Development Program of China (2017YFB0702400).

About author:: Liang Cheng received the M.S. degree in engineering from Central South University in 2012. After research working in China Academy of Engineering Physics from 2012 to 2016, he is pursuing the Ph.D. of Nuclear Fuel Cycle and Materials at Graduate School of China Academy of Engineering Physics under the supervision of Pengcheng Zhang. At present, his research has focused on accidental tolerant fuels and related materials.Pengcheng Zhang, Ph. D., senior research scientist, doctoral supervisor in Nuclear Fuel Cycle and Mate-rials, the outstanding experts in Sichuan Province, and State Council Expert for Special Allowance. He has been responsible for the National Key Research and Development Plan, the 863 Plan, the ITER Plan, the National Natural Science Foundation’s Key Project, the National Major Instrument Development Project, as well as awarded more than ten awards in provincial and ministerial level and army science and technology progress awards. His research interests include nuclear fuel materials, nuclear structural materials and advanced ceramics.

	Service
	E-mail this article
	Add to my bookshelf
	Add to citation manager
	E-mail Alert
	RSS
	Articles by authors
	CHENG Liang
	ZHANG

Cite this article:

CHENG Liang,ZHANG. Research Progress on Enhanced Thermal Conductivity Uranium Dioxide for Accident Tolerant Fuel[J]. Materials Reports, 2019, 33(11): 1787-1792.

URL:

http://www.mater-rep.com/EN/10.11896/cldb.18050107 OR http://www.mater-rep.com/EN/Y2019/V33/I11/1787

1 Li G X, Wu S. Nuclear fuel, Chemical Industry Press, China,2007(in Chinese).
李冠兴,武胜.核燃料,化学工业出版社,2007.
2 Fink J K. Journal of Nuclear Materials,2000,279(1),1.
3 Zinkle S J, Terrani K A, Gehin J C, et al. Journal of Nuclear Materials,2014,448(1-3),374.
4 Li B Q, Yang Z L, Jia J P, et al. Ceramics International,2018,44(9),10069.
5 Li B Q, Yang Z L, Jia J P, et al. Scripta Materialia,2018,142,70.
6 Chen Z C, Subhash G, Tulenko J S. Nuclear Engineering and Design,2015,294,52.
7 Kim D J, Kim K S, Kim D S, et al. Nuclear Engineering and Technology,2018,50(2),1.
8 Hyland G J. Journal of Nuclear Materials,1983,113(2-3),125.
9 Harding J H, Matin D G. Journal of Nuclear Materials,1989,166(3),223.
10 Yin Q, Savrasov S Y. Physical Review Letters,2008,100(22),225504(1).
11 Desgranges L, Ma Y, Garcia P, et al. Inorganic Chemistry,2017,56(1),321.
12 Gofryk K, Du S, Stanek C R, et al. Nature Communications,2014,5,4551.
13 Stehlea H, Assmanna H, Wunderlicha F. Nuclear Engineering and Design,1975,33(2),230.
14 Ge L, Subhash G, Baney R H, et al. Journal of the European Ceramic Society,2014,34(7),1791.
15 Yeo S, Mckenna E, Baney R, et al. Journal of Nuclear Materials,2013,433(1-3),66.
16 Yeo S, Baney R, Subhash G, et al. Journal of Nuclear Materials,2013,442(1-3),245.
17 Liu R, Zhou W, Prudil A, et al. Applied Thermal Engineering,2016,107,86.
18 Zhou W, Zhou W Z. Metals,2018,8(1),65.
19 Chandramouli D, Revankar S T. International Journal of Energy Research, DOI: 10.1155/2014/751070.
20 Zhou W Z, Liu R, Revankar S T. Annals of Nuclear Energy,2015,81,240.
21 Revankar S T, Zhou W Z, Chandramouli D. International Journal of Engineering Science,2015,5(1),1.
22 Liu R, Zhou W Z. Annals of Nuclear Energy,2017,109,298.
23 Chen Z C, Subhash G, Tulenko J S. Journal of Nuclear Materials,2016,475(16),1.
24 Kim S H, Joung C Y, Kim H S, et al. Journal of Nuclear Materials,2006,352(1-3),151.
25 Kim D J, Rhee Y W, Kim J H, et al. Journal of Nuclear Materials,2015,462,289.
26 Lee H S, Kim D J, Kim S W, et al. Journal of Nuclear Materials,2016,477,88.
27 Kim H G, Yang J H, Kim W J, et al. Nuclear Engineering and Technology,2016,48(1),1.
28 Lee Y H, No H C, Lee J I. Nuclear Engineering and Design,2017,31,213.
29 Kim D J, Lee H J, Jang C H, et al. Journal of Nuclear Materials,2017,492(1),6.
30 Charpentier L, Dawi K, Balat-pichelin M, et al. Corrosion Science,2012,59(3),127.
31 Braun J, Gueneau C, Alpettaz T, et al. Journal of Nuclear Materials,2017,487(1),380.
32 Matsumiya H, Yoshioka K, Kikuchi T, et al. Progress in Nuclear Energy,2015,82(1),16.
33 Cheng L, Zhang P C. Materials Review A:Review Papers,2018,32(7),34(in Chinese).
程亮,张鹏程.材料导报:综述篇,2018,32(7),34.
34 Tulenko J S, Baney R H. An innovative high thermal conductivity fuel design, Department of Energy Reports,2007.
35 Chauhan V S, Riyad M F, Du X P, et al. Metallurgical and Materials Transactions E,2017,4(2),61.
36 Nishigaki S, Maekawa K. Journal of Nuclear Materials,1964,14,453.
37 Ishimoto S, Hirai M, Ito K, et al. Journal of Nuclear Science and Technology,1996,33(2),134.
38 Sarma K H, Fourcade J, Lee S G, et al. Journal of Nuclear Materials,2006,352(1-3),324.
39 Garcia C B, Brito R A, Ortega L H, et al. Metallurgical and Materials Transactions E,2017,4(2-4),70.
40 Mccoy K, Mays C. Journal of Nuclear Materials,2008,375(2),157.
41 Hickman B S, Pryor A W. Journal of Nuclear Materials,1964,14(64),96.
42 Slack G A. Journal of Applied Physics,1964,35(12),3460.
43 Thumm M. Diamond and Related Materials,2001,10(9),1692.
44 Negre J P, Rubbelynck C. Nuclear Instruments and Methods in Physics Research Section A-Accelerators,2000,451(3),638.
45 Abyzov A M, Shakhov F M, Averkin A I, et al. Materials and Design,2015,87,527.
46 Ma S D, Zhao N Q, Shi C S, et al. Applied Surface Science,2017,402,372.
47 Liang X, Jia C, Chu K, et al. Journal of Composite Materials,2012,46(9),1127.
48 Ahn J, Tan F H, Tan H S. Journal of Materials Science Letters,1993,12(10),775.
49 Bundy F P, Bassett W A, Weathers M S, et al. Carbon,1996,34(2),141.
50 Qian J, Pantea C, Huang J, et al. Carbon,2004,42(12),2691.
51 Gosse S, Gueneau C, Alpettaz T, et al. Nuclear Engineering and Design,2008,238(11),2866.
52 Zaiser M, Lyutovich Y, Banhart F. Physical Review B,2000,62(5),3058.
53 Lyutovich Y, Banhart F. Applied Physics Letters,1999,74(5),659.
54 Zaiser M, Banhart F. Applied Physics Letters,1997,79(19),3680.
55 Cheng B, Chou P, Kim Y J. Journal of Nuclear Science and Technology,2016,2(5),1.
56 Cheng B, Kim Y J, Chou P. Journal of Nuclear Science and Technology,2016,48(1),16.
57 Nelson A T, Sooby E S, Kim Y J, et al. Journal of Nuclear Materials,2014,448(1-3),441.
58 Byun T S, Li M, Cockeram B V, et al. Journal of Nuclear Materials,2008,376(2),240.