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

Author:

Choi Hangbok1ORCID,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

Reference66 articles.

1. The Energy Multiplier Module (EM2): Status of Conceptual Design

2. “Development Status of Metallic, Dispersion and Non-Oxide Advanced and Alternative Fuels for Power and Research Reactors,” IAEA-TECDOC-1374, International Atomic Energy Agency (2003).

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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