Silicon carbide grain boundary distributions, irradiation conditions, and silver retention in irradiated AGR-1 TRISO fuel particles-Reference-Cited by-同舟云学术

Silicon carbide grain boundary distributions, irradiation conditions, and silver retention in irradiated AGR-1 TRISO fuel particles

Published:2018-04 Issue: Volume:329 Page:46-52
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Lillo T.M.,van Rooyen I.J.,Aguiar J.A.

Funder

United States Department of Energy, Office of Nuclear Energy, under United States Department of Energy Idaho Operations Office

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference39 articles.

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4. Demkowicz, P.A., Hunn, J.D., Morris, R.N., Van Rooyen, I.J., Gerczak, T., Harp, J.M., Ploger, S.A., 2015. AGR-1 Post Irradiation Examination Final Report, INL/EXT-15-36407, Revision 0.

5. Irradiation performance of AGR-1 high temperature reactor fuel;Demkowicz;Nucl. Eng. Design,2016

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1. Comparison of microstructural and micro-chemical evolutions in the irradiated fuel kernels of AGR-1 and AGR-2 TRISO fuel particles;Progress in Nuclear Energy;2024-11

2. EPMA-based mass balance method for quantitative fission product distribution comparison between TRISO particles;MRS Advances;2021-12

3. First principles analysis of impurities in silicon carbide grain boundaries;Acta Materialia;2021-12

4. Characterization of PyC/SiC Interfaces with FIB-SEM Tomography;Journal of Nuclear Materials;2021-03

5. Redistribution of radionuclides in irradiated AGR-1 UCO TRISO fuel after 1800 °C safety testing;Journal of Nuclear Materials;2020-12