Status report on HFIR irradiation of optimized alumina forming alloys

Annabelle G. Le Coq; David A. Collins; Nick G. Russell; Richard H. Howard; Holden C. Hyer; Sebastien N. Dryepondt; Cody C. Taylor; David T. Hoelzer; Caleb P. Massey

doi:10.2172/2333784

Status report on HFIR irradiation of optimized alumina forming alloys

Annabelle G. Le Coq, David A. Collins, Nick G. Russell, Richard H. Howard, Holden C. Hyer, Sebastien N. Dryepondt, Cody C. Taylor, David T. Hoelzer, Caleb P. Massey

Research output: Book/Report › Commissioned report

Abstract

Properties of FeCrAl alloys under neutron irradiation are of interest because of these materials’ potential application as accident-tolerant fuel cladding in nuclear systems. In parallel, alumina-forming austenitic (AFA) alloys are of interest for use as structural materials in advanced nuclear systems for their potential higher resistance to embrittlement and high-temperature steam oxidation resistance. An irradiation campaign for fiscal year 2024 has been developed under the Advanced Fuels Campaign to perform irradiation testing of various FeCrAl and AFA alloys in Oak Ridge National Laboratory’s High Flux Isotope Reactor (HFIR). The goals of this irradiation campaign are to (1) study the impact of minor alloying elements on the neutron-irradiated mechanical properties of FeCrAl alloys and (2) collect neutron-irradiated mechanical properties on AFA alloys for comparison with those of FeCrAl alloys. This campaign will include both tensile and fracture toughness specimens tested following HFIR irradiation at temperatures representative of normal operating conditions in light-water reactors. The pre-irradiation characterization to date, the irradiation plan for the FeCrAl and AFA specimens, and the subsequent post-irradiation experimental test plan are presented in this report, along with the status of HFIR builds and scheduled insertion dates.

Original language	English
Place of Publication	United States
DOIs	https://doi.org/10.2172/2333784
State	Published - Mar 2024

Keywords

36 MATERIALS SCIENCE

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10.2172/2333784

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title = "Status report on HFIR irradiation of optimized alumina forming alloys",

abstract = "Properties of FeCrAl alloys under neutron irradiation are of interest because of these materials{\textquoteright} potential application as accident-tolerant fuel cladding in nuclear systems. In parallel, alumina-forming austenitic (AFA) alloys are of interest for use as structural materials in advanced nuclear systems for their potential higher resistance to embrittlement and high-temperature steam oxidation resistance. An irradiation campaign for fiscal year 2024 has been developed under the Advanced Fuels Campaign to perform irradiation testing of various FeCrAl and AFA alloys in Oak Ridge National Laboratory{\textquoteright}s High Flux Isotope Reactor (HFIR). The goals of this irradiation campaign are to (1) study the impact of minor alloying elements on the neutron-irradiated mechanical properties of FeCrAl alloys and (2) collect neutron-irradiated mechanical properties on AFA alloys for comparison with those of FeCrAl alloys. This campaign will include both tensile and fracture toughness specimens tested following HFIR irradiation at temperatures representative of normal operating conditions in light-water reactors. The pre-irradiation characterization to date, the irradiation plan for the FeCrAl and AFA specimens, and the subsequent post-irradiation experimental test plan are presented in this report, along with the status of HFIR builds and scheduled insertion dates.",

keywords = "36 MATERIALS SCIENCE",

author = "{Le Coq}, {Annabelle G.} and Collins, {David A.} and Russell, {Nick G.} and Howard, {Richard H.} and Hyer, {Holden C.} and Dryepondt, {Sebastien N.} and Taylor, {Cody C.} and Hoelzer, {David T.} and Massey, {Caleb P.}",

year = "2024",

month = mar,

doi = "10.2172/2333784",

language = "English",

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T1 - Status report on HFIR irradiation of optimized alumina forming alloys

AU - Le Coq, Annabelle G.

AU - Collins, David A.

AU - Russell, Nick G.

AU - Howard, Richard H.

AU - Hyer, Holden C.

AU - Dryepondt, Sebastien N.

AU - Taylor, Cody C.

AU - Hoelzer, David T.

AU - Massey, Caleb P.

PY - 2024/3

Y1 - 2024/3

N2 - Properties of FeCrAl alloys under neutron irradiation are of interest because of these materials’ potential application as accident-tolerant fuel cladding in nuclear systems. In parallel, alumina-forming austenitic (AFA) alloys are of interest for use as structural materials in advanced nuclear systems for their potential higher resistance to embrittlement and high-temperature steam oxidation resistance. An irradiation campaign for fiscal year 2024 has been developed under the Advanced Fuels Campaign to perform irradiation testing of various FeCrAl and AFA alloys in Oak Ridge National Laboratory’s High Flux Isotope Reactor (HFIR). The goals of this irradiation campaign are to (1) study the impact of minor alloying elements on the neutron-irradiated mechanical properties of FeCrAl alloys and (2) collect neutron-irradiated mechanical properties on AFA alloys for comparison with those of FeCrAl alloys. This campaign will include both tensile and fracture toughness specimens tested following HFIR irradiation at temperatures representative of normal operating conditions in light-water reactors. The pre-irradiation characterization to date, the irradiation plan for the FeCrAl and AFA specimens, and the subsequent post-irradiation experimental test plan are presented in this report, along with the status of HFIR builds and scheduled insertion dates.

AB - Properties of FeCrAl alloys under neutron irradiation are of interest because of these materials’ potential application as accident-tolerant fuel cladding in nuclear systems. In parallel, alumina-forming austenitic (AFA) alloys are of interest for use as structural materials in advanced nuclear systems for their potential higher resistance to embrittlement and high-temperature steam oxidation resistance. An irradiation campaign for fiscal year 2024 has been developed under the Advanced Fuels Campaign to perform irradiation testing of various FeCrAl and AFA alloys in Oak Ridge National Laboratory’s High Flux Isotope Reactor (HFIR). The goals of this irradiation campaign are to (1) study the impact of minor alloying elements on the neutron-irradiated mechanical properties of FeCrAl alloys and (2) collect neutron-irradiated mechanical properties on AFA alloys for comparison with those of FeCrAl alloys. This campaign will include both tensile and fracture toughness specimens tested following HFIR irradiation at temperatures representative of normal operating conditions in light-water reactors. The pre-irradiation characterization to date, the irradiation plan for the FeCrAl and AFA specimens, and the subsequent post-irradiation experimental test plan are presented in this report, along with the status of HFIR builds and scheduled insertion dates.

KW - 36 MATERIALS SCIENCE

U2 - 10.2172/2333784

DO - 10.2172/2333784

M3 - Commissioned report

BT - Status report on HFIR irradiation of optimized alumina forming alloys

CY - United States

ER -

Status report on HFIR irradiation of optimized alumina forming alloys

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