AGR Fuel Oxidation Testing Summary and Plans

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.

Authors

John D Stempien (ORCID: https://orcid.org/0000-0001-6632-0785)

Institutions

Idaho National Laboratory (US)

Publication Details

Journal: OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Published: 2024-09-09
Primary Topic: Nuclear Materials and Properties
Type: article

Funders

U.S. Department of Energy
Battelle

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article

AGR Fuel Oxidation Testing Summary and Plans

John D Stempien

Sep 9, 2024

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

Nuclear Materials and Properties

article

AGR Fuel Oxidation Testing Summary and Plans

John D Stempien

September 9, 2024article en

Abstract

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

Idaho National Laboratory (US)

U.S. Department of Energy, Battelle

Nuclear Materials and Properties

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AGR Fuel Oxidation Testing Summary and Plans — John D Stempien · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) (2024) | TGRS Research Map | TGRS