Microstructure and thermal conductivity of fully ceramic microencapsulated fuel fabricated by spark plasma sintering-Reference-Cited by-同舟云学术

Microstructure and thermal conductivity of fully ceramic microencapsulated fuel fabricated by spark plasma sintering

Published:2018-04-18 Issue:9 Volume:101 Page:4224-4236
ISSN:0002-7820
Container-title:Journal of the American Ceramic Society
language:en
Short-container-title:J Am Ceram Soc

Author:

Cao Fangcheng¹,Fan Xiaohui¹,Liu Bing²,Zhao Xiaofeng¹^ORCID,Guo Fangwei¹^ORCID,Xiao Ping¹³

Affiliation:

1. School of Materials Science and Engineering Shanghai Jiao Tong University Shanghai China

2. Institute of Nuclear and New Energy Technology Tsinghua University Beijing China

3. School of Materials University of Manchester Manchester UK

Funder

National Natural Science Foundation of China

Publisher

Wiley

Subject

Materials Chemistry,Ceramics and Composites

Link

https://onlinelibrary.wiley.com/doi/pdf/10.1111/jace.15585

Reference33 articles.

1. Handbook of SiC properties for fuel performance modeling

2. A review of TRISO fuel performance models

3. Graphite, Ceramics, and Ceramic Composites for High-Temperature Nuclear Power Systems

4. Fully ceramic microencapsulated fuels: a transformational technology for present and next generation reactors‐properties and fabrication of FCM fuel;Snead LL;Trans Am Nucl Soc,2011

5. Fabrication and characterization of fully ceramic microencapsulated fuels

Cited by 22 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Study on thermodynamic equivalent performance of fully ceramic microencapsulated fuel based on representative volume element model;Frontiers in Energy Research;2024-08-13

2. Thermal conductivity of SiC and PyC coatings in spherical nuclear fuel particles measured by nanosecond time domain thermoreflectance;Journal of the European Ceramic Society;2024-06

3. Fabrication and properties of SiC-based accident-tolerant fuel with precisely-regulated TRISO particles dispersion;Journal of Physics: Conference Series;2024-04-01

4. Experimental techniques for investigating thermal transport in nuclear materials;Journal of Nuclear Science and Technology;2024-03-28

5. Pressureless sintering of large sized fully ceramic microencapsulated fuel pellets;Journal of Nuclear Materials;2024-02