Hydrothermal Corrosion Studies on Nitride Fuels

Brian J. Jaques; Jennifer Watkins; Thomas Braine; Beata Tyburska-Puschel; Peng Xu; Edward J. Lahoda; Darryl P. Butt

Hydrothermal Corrosion Studies on Nitride Fuels

Brian J. Jaques, Jennifer Watkins, Thomas Braine, Beata Tyburska-Puschel, Peng Xu, Edward J. Lahoda, Darryl P. Butt

Micron School of Materials Science and Engineering

Research output: Chapter in Book/Report/Conference proceeding › Chapter

1 Scopus citations

Abstract

Uranium mononitride (UN) has been identified as a candidate nuclear fuel for use in the current US light water reactor (LWR) fleet as well as in next generation nuclear plants (NGNP), largely due to its high uranium density and thermal conductivity. However, its hydrothermal corrosion performance in accident scenarios has not been thoroughly investigated. In this work, UN was synthesized using a hydride-dehydride-nitride thermal synthesis route prior to sintering into dense compacts (>90%TD). The compacts were corroded in a water filled autoclave up to 350 °C and 125 atm. The kinetics of corrosion were characterized through phase analysis, mass loss, and microstructural analysis.

Original language	American English
Title of host publication	Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance
State	Published - 1 Jan 2016

Keywords

corrosion
light water reactors
nitrides
nuclear reactor accidents
sintering

EGS Disciplines

Materials Science and Engineering

Cite this

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title = "Hydrothermal Corrosion Studies on Nitride Fuels",

abstract = " Uranium mononitride (UN) has been identified as a candidate nuclear fuel for use in the current US light water reactor (LWR) fleet as well as in next generation nuclear plants (NGNP), largely due to its high uranium density and thermal conductivity. However, its hydrothermal corrosion performance in accident scenarios has not been thoroughly investigated. In this work, UN was synthesized using a hydride-dehydride-nitride thermal synthesis route prior to sintering into dense compacts (>90%TD). The compacts were corroded in a water filled autoclave up to 350 °C and 125 atm. The kinetics of corrosion were characterized through phase analysis, mass loss, and microstructural analysis.",

keywords = "corrosion, light water reactors, nitrides, nuclear reactor accidents, sintering",

author = "Jaques, {Brian J.} and Jennifer Watkins and Thomas Braine and Beata Tyburska-Puschel and Peng Xu and Lahoda, {Edward J.} and Butt, {Darryl P.}",

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day = "1",

language = "American English",

booktitle = "Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance",

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TY - CHAP

T1 - Hydrothermal Corrosion Studies on Nitride Fuels

AU - Jaques, Brian J.

AU - Watkins, Jennifer

AU - Braine, Thomas

AU - Tyburska-Puschel, Beata

AU - Xu, Peng

AU - Lahoda, Edward J.

AU - Butt, Darryl P.

PY - 2016/1/1

Y1 - 2016/1/1

N2 - Uranium mononitride (UN) has been identified as a candidate nuclear fuel for use in the current US light water reactor (LWR) fleet as well as in next generation nuclear plants (NGNP), largely due to its high uranium density and thermal conductivity. However, its hydrothermal corrosion performance in accident scenarios has not been thoroughly investigated. In this work, UN was synthesized using a hydride-dehydride-nitride thermal synthesis route prior to sintering into dense compacts (>90%TD). The compacts were corroded in a water filled autoclave up to 350 °C and 125 atm. The kinetics of corrosion were characterized through phase analysis, mass loss, and microstructural analysis.

AB - Uranium mononitride (UN) has been identified as a candidate nuclear fuel for use in the current US light water reactor (LWR) fleet as well as in next generation nuclear plants (NGNP), largely due to its high uranium density and thermal conductivity. However, its hydrothermal corrosion performance in accident scenarios has not been thoroughly investigated. In this work, UN was synthesized using a hydride-dehydride-nitride thermal synthesis route prior to sintering into dense compacts (>90%TD). The compacts were corroded in a water filled autoclave up to 350 °C and 125 atm. The kinetics of corrosion were characterized through phase analysis, mass loss, and microstructural analysis.

KW - corrosion

KW - light water reactors

KW - nitrides

KW - nuclear reactor accidents

KW - sintering

UR - https://scholarworks.boisestate.edu/mse_facpubs/299

M3 - Chapter

BT - Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance

ER -

Hydrothermal Corrosion Studies on Nitride Fuels

Abstract

Keywords

EGS Disciplines

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