Measurement of kernel swelling and buffer densification in irradiated UCO-TRISO particles-Reference-Cited by-同舟云学术

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Measurement of kernel swelling and buffer densification in irradiated UCO-TRISO particles

Published:2017-04 Issue: Volume:486 Page:339-349
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Bower Gordon R.^ORCID,Ploger Scott A.,Demkowicz Paul A.,Hunn John D.

Funder

U.S. Department of Energy

Office of Nuclear Energy as part of the Advanced Gas Reactor Fuel Development and Qualification Program

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference20 articles.

1. The DOE advanced gas reactor fuel development and qualification program;Petti;JOM,2010

2. AGR-1 Irradiation Test Final As-run Report;Collin,2015

3. Paper 104, Proceedings of HTR-2010;Grover,2010

4. Fabrication of Baseline and Variant Particle Fuel for AGR-1;Lowden,2006

5. AGR-1 Fuel Compact Pre-irradiation Characterization Summary Report;Hunn,2012

Cited by 15 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. 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

2. Investigation on the Irradiation-thermal–mechanical coupling behaviors of the solid Microencapsulated fuel rod;Nuclear Engineering and Design;2023-12

3. Seeing the whole picture: Methods for getting the most from micro X-ray computed tomography of TRISO nuclear fuel particles;Tomography of Materials and Structures;2023-06

4. Effects of the mesostructures and irradiation conditions on the thermo-mechanical coupling behaviors in LWR-used fully ceramic-microencapsulated fuel pellets;Nuclear Materials and Energy;2023-03

5. Microstructural heterogeneity of the buffer layer of TRISO nuclear fuel particles;Journal of Nuclear Materials;2023-02

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