Redistribution of radionuclides in irradiated AGR-1 UCO TRISO fuel after 1800 °C safety testing-Reference-Cited by-同舟云学术

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Redistribution of radionuclides in irradiated AGR-1 UCO TRISO fuel after 1800 °C safety testing

Published:2020-12 Issue: Volume:542 Page:152453
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Gerczak Tyler J.,Seibert Rachel L.,Hunn John D.,Baldwin Charles A.,Montgomery Fred C.,Morris Robert N.

Publisher

Elsevier BV

Subject

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

Reference63 articles.

1. The DOE Advanced Gas Reactor Fuel Development and Qualification Program;Petti;J. Mater.,2006

2. Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: core design and safety analysis;Brown;Ann. Nucl. Energy.,2017

3. Microencapsulated fuel technology for commercial light water and advanced reactor application;Terrani;J. Nucl. Mater.,2012

4. A novel approach to fabricating fuel compacts for the next generation nuclear plant (NGNP);Pappano;J. Nucl. Mater.,2008

5. Fabrication of Baseline and Variant Particle Fuel for AGR-1, ORNL/CF 06/02;Lowden,2006

Cited by 5 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. Characterization of fluidized bed chemical vapor deposition ZrC coatings on PyC/YSZ kernels deposited under differing conditions;Journal of Nuclear Materials;2024-06

2. 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

3. High‐temperature oxidation behavior of the SiC layer of TRISO particles in low‐pressure oxygen;Journal of the American Ceramic Society;2023-02-15

4. Effect of ultra-high temperature treatment on microstructures and mechanical properties of TRISO particles;Journal of Nuclear Materials;2022-06

5. Effects of the key parameters of TRISO particle buffer layer on in-pile thermo-mechanical behavior in FCM fuel pellets;Journal of Nuclear Materials;2021-08

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