Fuel performance evaluation of two high burnup PWR core designs during normal operation, control rod withdrawal, and control rod ejection scenarios

Author:

Lindsay Isabelle O.ORCID,Fox MasonORCID,Sweet Ryan T.ORCID,Capps Nathan,Brown Nicholas R.ORCID

Funder

U.S. Department of Energy

Office of Nuclear Energy

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

Reference42 articles.

1. Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation;Barani;J. Nucl. Mater.,2020

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3. Brassfield, H C, J F White, L Sjodahl, and J T Bittel. 1968. “Recommended property and reaction kinetics data for use in evaluating a light-water-cooled reactor loss-of-coolant incident involving zircaloy-4- OR 304-SS-CLAD UO{sub 2}.” In, Medium: ED; Size: Pages: 89. United States.

4. Rod Internal Pressure Distribution and Uncertainty Analysis Using FRAPCON;Bratton;Nucl. Technol.,2017

5. The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors;Brown;Ann. Nucl. Energy,2017

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