Accident tolerant fuel cladding development: Promise, status, and challenges

Terrani, Kurt A.

doi:10.1016/j.jnucmat.2017.12.043

Title: Accident tolerant fuel cladding development: Promise, status, and challenges

Abstract

The motivation for transitioning away from zirconium-based fuel cladding in light water reactors to significantly more oxidation-resistant materials, thereby enhancing safety margins during severe accidents, is laid out. A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding, and silicon carbide fiber–reinforced silicon carbide matrix composite cladding, is offered. Technical challenges and data gaps for each of these cladding technologies are highlighted. Full development towards commercial deployment of these technologies is identified as a high priority for the nuclear industry.

Authors:

Terrani, Kurt A. ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Publication Date:: Sat Jan 13 00:00:00 EST 2018

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

OSTI Identifier:: 1471930

Alternate Identifier(s):: OSTI ID: 1506714

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Journal Article: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 501; Journal Issue: C; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 36 MATERIALS SCIENCE

Citation Formats


                    Terrani, Kurt A. Accident tolerant fuel cladding development: Promise, status, and challenges.  United States: N. p., 2018. 
        Web.  doi:10.1016/j.jnucmat.2017.12.043.

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                    Terrani, Kurt A. Accident tolerant fuel cladding development: Promise, status, and challenges.  United States.  https://doi.org/10.1016/j.jnucmat.2017.12.043

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                    Terrani, Kurt A. 2018.  
        "Accident tolerant fuel cladding development: Promise, status, and challenges".  United States.  https://doi.org/10.1016/j.jnucmat.2017.12.043.  https://www.osti.gov/servlets/purl/1471930.

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@article{osti_1471930,

  title        = {Accident tolerant fuel cladding development: Promise, status, and challenges},

  author       = {Terrani, Kurt A.},

  abstractNote = {The motivation for transitioning away from zirconium-based fuel cladding in light water reactors to significantly more oxidation-resistant materials, thereby enhancing safety margins during severe accidents, is laid out. A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding, and silicon carbide fiber–reinforced silicon carbide matrix composite cladding, is offered. Technical challenges and data gaps for each of these cladding technologies are highlighted. Full development towards commercial deployment of these technologies is identified as a high priority for the nuclear industry.},

  doi          = {10.1016/j.jnucmat.2017.12.043},

  url          = {https://www.osti.gov/biblio/1471930},
  journal      = {Journal of Nuclear Materials},

  issn         = {0022-3115},

  number       = C,

  volume       = 501,

  place        = {United States},

  year         = {Sat Jan 13 00:00:00 EST 2018},

  month        = {Sat Jan 13 00:00:00 EST 2018}

}

Copy to clipboard

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Figure 1.: Thermal power and cumulative energy due to radionuclide decay heat and Zr-based cladding oxidation heat during a short-term station blackout.

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Works referencing / citing this record:

Hydrogen Interaction with Deep Surface Modified Zr-1Nb Alloy by High Intensity Ti Ion Implantation
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Kashkarov, Egor; Ryabchikov, Alexander; Kurochkin, Alexander
Metals, Vol. 8, Issue 12
https://doi.org/10.3390/met8121081

Oxidation Characteristics of Two FeCrAl Alloys in Air and Steam from 800°C to 1300°C
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Rebak, Raul B.; Gupta, Vipul K.; Larsen, Michael
JOM, Vol. 70, Issue 8
https://doi.org/10.1007/s11837-018-2979-9

Effectiveness of Cr-Coated Zr-Alloy Clad in Delaying Fuel Degradation for a PWR During a Station Blackout Event
journal, August 2019

Wang, J.; Yeom, H.; Humrickhouse, P.
Nuclear Technology, Vol. 206, Issue 3
https://doi.org/10.1080/00295450.2019.1649566

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Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding

Conference Khalifa, H.; Sheeder, J.; Jacobsen, G.; ...

Silicon carbide (SiC) and silicon carbide fiber reinforced, silicon carbide matrix (SiC-SiC) composites are candidate materials for nuclear fuel cladding in accident tolerant light water reactors and advanced high temperature reactors due to their chemical stability and retention of strength at elevated temperature and neutron flux. A reliable means to join silicon carbide components is imperative to the successful implementation of SiC-based structural nuclear materials as fuel cladding as well as more complex core internal structures. A comprehensive approach has been taken to address several of the significant challenges associated with SiC joining and fabrication of complex SiC structures. Thismore »« less
Phase Equilibria and Thermochemistry of Advanced Fuels: Modeling Burnup Behavior (Final Report)

Technical Report Besmann, Theodore; McMurrary, Jake; Nelson, Andrew; ...

Achieving the goal of developing advanced fuel concepts that meet the DOE objectives of being robust, demonstrating high performance, and are more tolerant of accident conditions than current fuel systems will require a thorough understanding of the thermophysical and thermochemical properties of the constituent materials. Non-oxide fuel systems are being explored under the Advanced Fuels Program that hold significant promise for improved performance and accident tolerance, including the uranium silicide-based system considered in the current work. Prospective cladding materials currently considered that contribute to improved accident tolerance include silicon carbide composites and ferritic alloys (Fe-Cr-Al base compositions). Thus, the effortmore »« less
https://doi.org/10.2172/1606266

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Title: Accident tolerant fuel cladding development: Promise, status, and challenges

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Thermal Neutron Capture Cross Sections journal, August 1951

Advanced oxidation-resistant iron-based alloys for LWR fuel cladding journal, May 2014

The Future of Low-Carbon Electricity journal, October 2017

Fuel R & D to Improve Fuel Reliability journal, September 2006

Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding journal, July 2015

Accident tolerant fuels for LWRs: A perspective journal, May 2014

Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions journal, May 2014

Scoping assessments of ATF impact on late-stage accident progression including molten core–concrete interaction journal, May 2014

Modification of MELCOR for severe accident analysis of candidate accident tolerant cladding materials journal, April 2017

Research and Development Methodology for Practical Use of Accident Tolerant Fuel in Light Water Reactors journal, February 2016

KAERI’s Development of LWR Accident-Tolerant Fuel journal, May 2014

Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure journal, August 2012

High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments journal, September 2013

Silicon Carbide Oxidation in Steam up to 2 MPa journal, July 2014

Oxidation of Advanced Zirconium Cladding Alloys in Steam at Temperatures in the Range of 600–1200 °C journal, March 2011

The Effect of Oxide Volatilization on the Oxidation Kinetics of Cr and Fe-Cr Alloys journal, January 1966

Alumina Volatility in Water Vapor at Elevated Temperatures journal, September 2004

The effect of H2O gas on volatilities of planet-forming major elements: I. Experimental determination of thermodynamic properties of Ca-, Al-, and Si-hydroxide gas molecules and its application to the solar nebula journal, January 1992

Mechanisms of irradiation growth of alpha-zirconium alloys journal, October 1988

Irradiation-induced densification of UO2 pellet fuel journal, November 1976

Experimental Observations on Fuel Pellet Performance at High Burnup journal, September 2006

Pellet-clad interaction (PCI) failures of zirconium alloy fuel cladding — A review journal, August 1990

Cracking of cladding tubes caused by power ramping and by laboratory stress corrosion experiments journal, December 1979

The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors journal, January 2017

Radiation-Induced Creep of UO2 journal, March 1973

Development of microstructure and irradiation hardening of Zircaloy during low dose neutron irradiation at nominally 358°C journal, November 2011

Development of microstructure and irradiation hardening of Zircaloy during low dose neutron irradiation at nominally 377–440°C journal, June 2014

Tensile properties of candidate SNS target container materials after proton and neutron irradiation in the LANSCE accelerator journal, July 2001

Investigation of Hydride Rim Effect on Failure of Zircaloy-4 Cladding with Tube Burst Test journal, January 2005

Materials challenges in nuclear energy journal, February 2013

Fuels for sodium-cooled fast reactors: US perspective journal, September 2007

Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics journal, August 2014

The effect of fuel thermal conductivity on the behavior of LWR cores during loss-of-coolant accidents journal, May 2014

Failure of high burnup fuels under reactivity-initiated accident conditions journal, April 2009

Comparative Analysis of Station Blackout Accident Progression in Typical pwr, bwr, and phwr journal, April 2012

Current knowledge on core degradation phenomena, a review journal, April 1999

Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings journal, August 2017

Mechanical analysis of surface-coated zircaloy cladding journal, August 2017

Neutronic evaluation of coating and cladding materials for accident tolerant fuels journal, April 2016

Critical heat flux for SiC- and Cr-coated plates under atmospheric condition journal, February 2015

Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating journal, October 2015

Investigation of the impact of coatings on corrosion and hydrogen uptake of Zircaloy-4 journal, December 2015

Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air journal, October 2015

High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings journal, October 2015

Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions journal, December 2016

Designing Radiation Resistance in Materials for Fusion Energy journal, July 2014

Prototypical experiments relating to air oxidation of Zircaloy-4 at high temperatures journal, August 2009

The MN+1AXN phases: A new class of solids: Thermodynamically stable nanolaminates journal, January 2000

Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding journal, November 2015

Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate journal, September 2016

Ceramic coating for corrosion (c3) resistance of nuclear fuel cladding journal, November 2015

Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding journal, September 2016

Protection of zirconium by alumina- and chromia-forming iron alloys under high-temperature steam exposure journal, July 2013

Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2–Ti5Al2C3 materials journal, March 2016

Phase stability, swelling, microstructure and strength of Ti3SiC2-TiC ceramics after low dose neutron irradiation journal, January 2017

Undoped and ytterbium-doped titanium aluminum nitride coatings for improved oxidation behavior of nuclear fuel cladding journal, December 2017

Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors journal, May 1984

Steam Oxidation Evaluation of Fe–Cr Alloys for Accident Tolerant Nuclear Fuel Cladding journal, March 2017

The 885° f (475° c) embrittlement of ferritic stainless steels journal, January 1973

α′ precipitation in neutron-irradiated Fe–Cr alloys journal, March 2014

Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors journal, January 2015

The development of alumina-forming austenitic stainless steels for high-temperature structural use journal, July 2008

Effect of steam on high temperature oxidation behaviour of alumina-forming alloys journal, January 2015

Performance of FeCrAl for accident-tolerant fuel cladding in high-temperature steam journal, August 2017

Effect of Al and Cr Content on Air and Steam Oxidation of FeCrAl Alloys and Commercial APMT Alloy journal, March 2017

Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors journal, December 2015

Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys journal, October 2015

Irradiation-enhanced α′ precipitation in model FeCrAl alloys journal, April 2016

A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys journal, May 2017

Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys journal, June 2017

Microstructure and environmental resistance of low Cr ODS FeCrAl journal, January 2015

Performance degradation of candidate accident-tolerant cladding under corrosive environment journal, August 2017

Design, properties, and weldability of advanced oxidation-resistant FeCrAl alloys journal, September 2017

Solid-liquid phase equilibria of Fe-Cr-Al alloys and spinels journal, August 2017

Microstructural control of FeCrAl alloys using Mo and Nb additions journal, October 2017

Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication journal, July 2017

Thermal Neutron Capture Cross Sections
journal, August 1951

Advanced oxidation-resistant iron-based alloys for LWR fuel cladding
journal, May 2014

The Future of Low-Carbon Electricity
journal, October 2017

Fuel R & D to Improve Fuel Reliability
journal, September 2006

Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding
journal, July 2015

Accident tolerant fuels for LWRs: A perspective
journal, May 2014

Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions
journal, May 2014

Scoping assessments of ATF impact on late-stage accident progression including molten core–concrete interaction
journal, May 2014

Modification of MELCOR for severe accident analysis of candidate accident tolerant cladding materials
journal, April 2017

Research and Development Methodology for Practical Use of Accident Tolerant Fuel in Light Water Reactors
journal, February 2016

KAERI’s Development of LWR Accident-Tolerant Fuel
journal, May 2014

Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure
journal, August 2012

High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments
journal, September 2013

Silicon Carbide Oxidation in Steam up to 2 MPa
journal, July 2014

Oxidation of Advanced Zirconium Cladding Alloys in Steam at Temperatures in the Range of 600–1200 °C
journal, March 2011

The Effect of Oxide Volatilization on the Oxidation Kinetics of Cr and Fe-Cr Alloys
journal, January 1966

Alumina Volatility in Water Vapor at Elevated Temperatures
journal, September 2004

The effect of H2O gas on volatilities of planet-forming major elements: I. Experimental determination of thermodynamic properties of Ca-, Al-, and Si-hydroxide gas molecules and its application to the solar nebula
journal, January 1992

Mechanisms of irradiation growth of alpha-zirconium alloys
journal, October 1988

Irradiation-induced densification of UO2 pellet fuel
journal, November 1976

Experimental Observations on Fuel Pellet Performance at High Burnup
journal, September 2006

Pellet-clad interaction (PCI) failures of zirconium alloy fuel cladding — A review
journal, August 1990

Cracking of cladding tubes caused by power ramping and by laboratory stress corrosion experiments
journal, December 1979

The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors
journal, January 2017

Radiation-Induced Creep of UO2
journal, March 1973

Development of microstructure and irradiation hardening of Zircaloy during low dose neutron irradiation at nominally 358°C
journal, November 2011

Development of microstructure and irradiation hardening of Zircaloy during low dose neutron irradiation at nominally 377–440°C
journal, June 2014

Tensile properties of candidate SNS target container materials after proton and neutron irradiation in the LANSCE accelerator
journal, July 2001

Investigation of Hydride Rim Effect on Failure of Zircaloy-4 Cladding with Tube Burst Test
journal, January 2005

Materials challenges in nuclear energy
journal, February 2013

Fuels for sodium-cooled fast reactors: US perspective
journal, September 2007

Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics
journal, August 2014

The effect of fuel thermal conductivity on the behavior of LWR cores during loss-of-coolant accidents
journal, May 2014

Failure of high burnup fuels under reactivity-initiated accident conditions
journal, April 2009

Comparative Analysis of Station Blackout Accident Progression in Typical pwr, bwr, and phwr
journal, April 2012

Current knowledge on core degradation phenomena, a review
journal, April 1999

Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings
journal, August 2017

Mechanical analysis of surface-coated zircaloy cladding
journal, August 2017

Neutronic evaluation of coating and cladding materials for accident tolerant fuels
journal, April 2016

Critical heat flux for SiC- and Cr-coated plates under atmospheric condition
journal, February 2015

Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating
journal, October 2015

Investigation of the impact of coatings on corrosion and hydrogen uptake of Zircaloy-4
journal, December 2015

Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air
journal, October 2015

High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings
journal, October 2015

Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions
journal, December 2016

Designing Radiation Resistance in Materials for Fusion Energy
journal, July 2014

Prototypical experiments relating to air oxidation of Zircaloy-4 at high temperatures
journal, August 2009

The M_N+1AX_N phases: A new class of solids: Thermodynamically stable nanolaminates
journal, January 2000

Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding
journal, November 2015

Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate
journal, September 2016

Ceramic coating for corrosion (c3) resistance of nuclear fuel cladding
journal, November 2015

Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding
journal, September 2016

Protection of zirconium by alumina- and chromia-forming iron alloys under high-temperature steam exposure
journal, July 2013

Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2–Ti5Al2C3 materials
journal, March 2016

Phase stability, swelling, microstructure and strength of Ti3SiC2-TiC ceramics after low dose neutron irradiation
journal, January 2017

Undoped and ytterbium-doped titanium aluminum nitride coatings for improved oxidation behavior of nuclear fuel cladding
journal, December 2017

Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors
journal, May 1984

Steam Oxidation Evaluation of Fe–Cr Alloys for Accident Tolerant Nuclear Fuel Cladding
journal, March 2017

The 885° f (475° c) embrittlement of ferritic stainless steels
journal, January 1973

α′ precipitation in neutron-irradiated Fe–Cr alloys
journal, March 2014

Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors
journal, January 2015

The development of alumina-forming austenitic stainless steels for high-temperature structural use
journal, July 2008

Effect of steam on high temperature oxidation behaviour of alumina-forming alloys
journal, January 2015

Performance of FeCrAl for accident-tolerant fuel cladding in high-temperature steam
journal, August 2017

Effect of Al and Cr Content on Air and Steam Oxidation of FeCrAl Alloys and Commercial APMT Alloy
journal, March 2017

Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
journal, December 2015

Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys
journal, October 2015

Irradiation-enhanced α′ precipitation in model FeCrAl alloys
journal, April 2016

A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys
journal, May 2017

Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys
journal, June 2017

Microstructure and environmental resistance of low Cr ODS FeCrAl
journal, January 2015

Performance degradation of candidate accident-tolerant cladding under corrosive environment
journal, August 2017

Design, properties, and weldability of advanced oxidation-resistant FeCrAl alloys
journal, September 2017

Solid-liquid phase equilibria of Fe-Cr-Al alloys and spinels
journal, August 2017

Microstructural control of FeCrAl alloys using Mo and Nb additions
journal, October 2017

Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication
journal, July 2017

Development of ODS FeCrAl for Compatibility in Fusion and Fission Energy Applications
journal, November 2014

Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions
journal, April 2017

Deformation behavior of laser welds in high temperature oxidation resistant Fe–Cr–Al alloys for fuel cladding applications
journal, November 2014

Uniform corrosion of FeCrAl alloys in LWR coolant environments
journal, October 2016