Performance Analysis of Silicon Carbide Composite Clad Uranium Carbide Fuel for a Long-Life Gas-Cooled Fast Reactor Under Normal Operation—Part I: Design Criteria and Material Data-Reference-Cited by-同舟云学术

Performance Analysis of Silicon Carbide Composite Clad Uranium Carbide Fuel for a Long-Life Gas-Cooled Fast Reactor Under Normal Operation—Part I: Design Criteria and Material Data

Published:2020-01-31 Issue:7 Volume:206 Page:993-1009
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Choi Hangbok¹^ORCID,Schleicher Robert W.¹,Bolin John¹

Affiliation:

1. General Atomics, 3550 General Atomics Court, San Diego, California 92121-1122

Funder

U.S. Department of Energy

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2019.1698936

Reference66 articles.

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3. J. O. BARNER, “Behavior of Sodium-Bonded (U,Pu)C Fuel Elements After Moderate Burnup,” LA-4669-MS, Los Alamos National Laboratory (1971).

4. R. D. BAKER, “Advanced Plutonium Fuels Program,” LA-5781-PR, Los Alamos National Laboratory (1974).

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