Work

AGR Fuel Oxidation Testing Summary and Plans

Year: 2024

Type: article

Abstract: This presentation describes the goals, scope, and plans for oxidation testing of (primarily irradiated) AGR TRISO fuels and related materials (such as graphite and graphitic matrix material). This presentation will be given at the annual program review meeting for the Gas-cooled Reactor program hosted at INL starting on July 16.

Source: OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)

Author: Stempien, John D [Idaho National Laboratory]

Institution: Idaho National Laboratory

Language: English

Topic: Graphite, nuclear technology, radiation studies

Subfield: Materials Chemistry

Field: Materials Science

Domain: Physical Sciences

Open Access status: green

Funders: U.S. Department of Energy, Battelle

OpenAlex ID: W4402698562

FWCI:

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