Oxidation Testing and Examination of AGR-2 Particles

Darren J. Skitt; Rachel L. Seibert; Tyler J. Gerczak; John D. Hunn; Zachary M. Burns; Grant W. Helmreich

doi:10.2172/1822055

Oxidation Testing and Examination of AGR-2 Particles

Darren J. Skitt
, Rachel L. Seibert
, Tyler J. Gerczak
, John D. Hunn
, Zachary M. Burns
, Grant W. Helmreich

Research output: Other contribution › Technical Report

Abstract

Post-irradiation examination (PIE) oxidation testing is being performed at Oak Ridge National Laboratory (ORNL) on fuel particles from the second Advanced Gas Reactor (AGR) irradiation experiment (AGR-2). Tristructural isotropic (TRISO)-coated particles containing mixed uranium carbide and uranium oxide (UCO) fuel kernels were taken from AGR-2 Compact 5-4-2 and heated in the Furnace for Irradiated TRISO Testing (FITT) under varying oxidizing conditions. Details on Compact 5-4-2 PIE can be found in a previous report (Hunn et al. 2018).

Original language	English
Place of Publication	United States
DOIs	https://doi.org/10.2172/1822055
State	Published - 2021

Keywords

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

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10.2172/1822055

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title = "Oxidation Testing and Examination of AGR-2 Particles",

abstract = "Post-irradiation examination (PIE) oxidation testing is being performed at Oak Ridge National Laboratory (ORNL) on fuel particles from the second Advanced Gas Reactor (AGR) irradiation experiment (AGR-2). Tristructural isotropic (TRISO)-coated particles containing mixed uranium carbide and uranium oxide (UCO) fuel kernels were taken from AGR-2 Compact 5-4-2 and heated in the Furnace for Irradiated TRISO Testing (FITT) under varying oxidizing conditions. Details on Compact 5-4-2 PIE can be found in a previous report (Hunn et al. 2018).",

keywords = "11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS, 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS",

author = "Skitt, \{Darren J.\} and Seibert, \{Rachel L.\} and Gerczak, \{Tyler J.\} and Hunn, \{John D.\} and Burns, \{Zachary M.\} and Helmreich, \{Grant W.\}",

year = "2021",

doi = "10.2172/1822055",

language = "English",

type = "Other",

}

TY - GEN

T1 - Oxidation Testing and Examination of AGR-2 Particles

AU - Skitt, Darren J.

AU - Seibert, Rachel L.

AU - Gerczak, Tyler J.

AU - Hunn, John D.

AU - Burns, Zachary M.

AU - Helmreich, Grant W.

PY - 2021

Y1 - 2021

N2 - Post-irradiation examination (PIE) oxidation testing is being performed at Oak Ridge National Laboratory (ORNL) on fuel particles from the second Advanced Gas Reactor (AGR) irradiation experiment (AGR-2). Tristructural isotropic (TRISO)-coated particles containing mixed uranium carbide and uranium oxide (UCO) fuel kernels were taken from AGR-2 Compact 5-4-2 and heated in the Furnace for Irradiated TRISO Testing (FITT) under varying oxidizing conditions. Details on Compact 5-4-2 PIE can be found in a previous report (Hunn et al. 2018).

AB - Post-irradiation examination (PIE) oxidation testing is being performed at Oak Ridge National Laboratory (ORNL) on fuel particles from the second Advanced Gas Reactor (AGR) irradiation experiment (AGR-2). Tristructural isotropic (TRISO)-coated particles containing mixed uranium carbide and uranium oxide (UCO) fuel kernels were taken from AGR-2 Compact 5-4-2 and heated in the Furnace for Irradiated TRISO Testing (FITT) under varying oxidizing conditions. Details on Compact 5-4-2 PIE can be found in a previous report (Hunn et al. 2018).

KW - 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

KW - 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

U2 - 10.2172/1822055

DO - 10.2172/1822055

M3 - Technical Report

CY - United States

ER -

Oxidation Testing and Examination of AGR-2 Particles

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Keywords

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