Modern nanostructured ferritic alloys: A compelling and viable choice for sodium fast reactor fuel cladding applications

Hoelzer, David T.; Massey, Caleb P.; Zinkle, Steven J.; Crawford, Doug C.; Terrani, Kurt A.

doi:10.1016/j.jnucmat.2019.151928

Title: Modern nanostructured ferritic alloys: A compelling and viable choice for sodium fast reactor fuel cladding applications

Abstract

Sodium fast reactor cores present a truly challenging environment for the fuel cladding and core structural materials that limit achievable fuel burnup in these systems. Modern nanostructured ferritic alloys have the potential to deliver the desired high performance characteristics where historic austenitic and ferritic/martensitic alloys fall short. Herein, a new nanostructured ferritic alloy, OFRAC (Oak Ridge Fast Reactor Advanced Fuel Cladding), is developed and demonstrated in cladding geometry with a length > 1 m. The alloy composition and microstructure are tailored to deliver dramatically improved strength and creep resistance. At 600 °C the ultimate tensile strength is ~600 MPa and the stress to induce a steady state strain rate of 10^-6 s^-1 is 500 MPa vs. 200 MPa for traditional ferritic/martensitic alloys. A very high defect sink density was engineered in these alloys that is expected to further enhance the traditional good swelling and irradiation creep resistance of ferritic/martensitic steels. These significant improvements along with the demonstrated viability for seamless cladding production indicate that this alloy is a compelling and viable choice for sodium fast reactor fuel cladding applications.

Authors:

^[1]; Massey, Caleb P. ^[1]; Zinkle, Steven J. ^[2]; Crawford, Doug C. ^[3];

^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)

Publication Date:: 2019-11-28

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

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

OSTI Identifier:: 1607116

Alternate Identifier(s):: OSTI ID: 1581011

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 529; Journal Issue: C; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 36 MATERIALS SCIENCE; Sodium fast reactor; Nanostructured ferritic alloy; OFRAC; Thin wall tubing; Tensile and creep properties

Citation Formats


                    Hoelzer, David T., Massey, Caleb P., Zinkle, Steven J., Crawford, Doug C., and Terrani, Kurt A. Modern nanostructured ferritic alloys: A compelling and viable choice for sodium fast reactor fuel cladding applications.  United States: N. p., 2019. 
Web.  doi:10.1016/j.jnucmat.2019.151928.

Copy to clipboard


                    Hoelzer, David T., Massey, Caleb P., Zinkle, Steven J., Crawford, Doug C., & Terrani, Kurt A. Modern nanostructured ferritic alloys: A compelling and viable choice for sodium fast reactor fuel cladding applications.  United States.  https://doi.org/10.1016/j.jnucmat.2019.151928

Copy to clipboard


                    Hoelzer, David T., Massey, Caleb P., Zinkle, Steven J., Crawford, Doug C., and Terrani, Kurt A. Thu .  
"Modern nanostructured ferritic alloys: A compelling and viable choice for sodium fast reactor fuel cladding applications".  United States.  https://doi.org/10.1016/j.jnucmat.2019.151928.  https://www.osti.gov/servlets/purl/1607116.

Copy to clipboard


                    
@article{osti_1607116,

  title        = {Modern nanostructured ferritic alloys: A compelling and viable choice for sodium fast reactor fuel cladding applications},

  author       = {Hoelzer, David T. and Massey, Caleb P. and Zinkle, Steven J. and Crawford, Doug C. and Terrani, Kurt A.},

  abstractNote = {Sodium fast reactor cores present a truly challenging environment for the fuel cladding and core structural materials that limit achievable fuel burnup in these systems. Modern nanostructured ferritic alloys have the potential to deliver the desired high performance characteristics where historic austenitic and ferritic/martensitic alloys fall short. Herein, a new nanostructured ferritic alloy, OFRAC (Oak Ridge Fast Reactor Advanced Fuel Cladding), is developed and demonstrated in cladding geometry with a length > 1 m. The alloy composition and microstructure are tailored to deliver dramatically improved strength and creep resistance. At 600 °C the ultimate tensile strength is ~600 MPa and the stress to induce a steady state strain rate of 10-6 s-1 is 500 MPa vs. 200 MPa for traditional ferritic/martensitic alloys. A very high defect sink density was engineered in these alloys that is expected to further enhance the traditional good swelling and irradiation creep resistance of ferritic/martensitic steels. These significant improvements along with the demonstrated viability for seamless cladding production indicate that this alloy is a compelling and viable choice for sodium fast reactor fuel cladding applications.},

  doi          = {10.1016/j.jnucmat.2019.151928},

  journal      = {Journal of Nuclear Materials},

  number       = C,

  volume       = 529,

  place        = {United States},

  year         = {2019},

  month        = {11}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (Publisher)

Accepted Manuscript (DOE)

Publisher's Version of Record

https://doi.org/10.1016/j.jnucmat.2019.151928

Other availability

Search WorldCat to find libraries that may hold this journal

Citation Metrics:

Cited by: 17 works

Citation information provided by
Web of Science

Save / Share:

Export Metadata

Save to My Library

Works referenced in this record:

Structural materials challenges for advanced reactor systems
journal, March 2009

Yvon, P.; Carré, F.
Journal of Nuclear Materials, Vol. 385, Issue 2
DOI: 10.1016/j.jnucmat.2008.11.026

Sodium fast reactor evaluation: Core materials
journal, July 2009

Cheon, Jin Sik; Lee, Chan Bock; Lee, Byoung Oon
Journal of Nuclear Materials, Vol. 392, Issue 2
DOI: 10.1016/j.jnucmat.2009.03.021

Structural materials for fission & fusion energy
journal, November 2009

Zinkle, Steven J.; Busby, Jeremy T.
Materials Today, Vol. 12, Issue 11
DOI: 10.1016/S1369-7021(09)70294-9

Materials challenges in nuclear energy
journal, February 2013

Zinkle, S. J.; Was, G. S.
Acta Materialia, Vol. 61, Issue 3
DOI: 10.1016/j.actamat.2012.11.004

French and United Kingdom Experience of High-Burnup Mixed-Oxide Fuel in Sodium-Cooled Fast Breeder Reactors
journal, January 2008

Martin, Philippe; Pelletier, Michel; Every, Denis
Nuclear Technology, Vol. 161, Issue 1
DOI: 10.13182/NT08-A3911

Structural materials for next generation nuclear systems: Challenges and the path forward
journal, December 2015

Yvon, Pascal; Le Flem, Marion; Cabet, Céline
Nuclear Engineering and Design, Vol. 294
DOI: 10.1016/j.nucengdes.2015.09.015

Motivation for utilizing new high-performance advanced materials in nuclear energy systems
journal, December 2016

Zinkle, S. J.; Terrani, K. A.; Snead, L. L.
Current Opinion in Solid State and Materials Science, Vol. 20, Issue 6
DOI: 10.1016/j.cossms.2016.10.004

A Once-Through Fuel Cycle for Fast Reactors
journal, July 2010

Weaver, Kevan D.; Gilleland, John; Ahlfeld, Charles
Journal of Engineering for Gas Turbines and Power, Vol. 132, Issue 10
DOI: 10.1115/1.4000898

Ferritic/martensitic steels for next-generation reactors
journal, September 2007

Klueh, R. L.; Nelson, A. T.
Journal of Nuclear Materials, Vol. 371, Issue 1-3
DOI: 10.1016/j.jnucmat.2007.05.005

An overview of neutron irradiation effects in LMFBR materials
journal, July 1982

Straalsund, J. L.; Powell, R. W.; Chin, B. A.
Journal of Nuclear Materials, Vol. 108-109
DOI: 10.1016/0022-3115(82)90499-8

Austenitic stainless steels with improved resistance to radiation-induced swelling
journal, April 1976

Bloom, E. E.; Stiegler, J. O.; Rowcliffe, A. F.
Scripta Metallurgica, Vol. 10, Issue 4
DOI: 10.1016/0036-9748(76)90081-8

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

Walters, Leon C.; Seidel, B. R.; Kittel, J. Howard
Nuclear Technology, Vol. 65, Issue 2
DOI: 10.13182/NT84-A33408

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

Crawford, Douglas C.; Porter, Douglas L.; Hayes, Steven L.
Journal of Nuclear Materials, Vol. 371, Issue 1-3
DOI: 10.1016/j.jnucmat.2007.05.010

A US perspective on fast reactor fuel fabrication technology and experience part I: metal fuels and assembly design
journal, June 2009

Burkes, Douglas E.; Fielding, Randall S.; Porter, Douglas L.
Journal of Nuclear Materials, Vol. 389, Issue 3
DOI: 10.1016/j.jnucmat.2009.02.035

Metal fuel test program in the FFTF
journal, September 1993

Pitner, A. L.; Baker, R. B.
Journal of Nuclear Materials, Vol. 204
DOI: 10.1016/0022-3115(93)90208-G

Metallic fuels for advanced reactors
journal, July 2009

Carmack, W. J.; Porter, D. L.; Chang, Y. I.
Journal of Nuclear Materials, Vol. 392, Issue 2
DOI: 10.1016/j.jnucmat.2009.03.007

Status of LMR fuel development in the United States of America
journal, September 1993

Leggett, R. D.; Walters, L. C.
Journal of Nuclear Materials, Vol. 204
DOI: 10.1016/0022-3115(93)90195-5

A US perspective on fast reactor fuel fabrication technology and experience. Part II: Ceramic fuels
journal, August 2009

Burkes, Douglas E.; Fielding, Randall S.; Porter, Douglas L.
Journal of Nuclear Materials, Vol. 393, Issue 1
DOI: 10.1016/j.jnucmat.2009.04.023

History of fast reactor fuel development
journal, September 1993

Kittel, J. H.; Frost, B. R. T.; Mustelier, J. P.
Journal of Nuclear Materials, Vol. 204
DOI: 10.1016/0022-3115(93)90193-3

Experience with advanced driver fuels in EBR-II
journal, September 1993

Lahm, C. E.; Koenig, J. F.; Pahl, R. G.
Journal of Nuclear Materials, Vol. 204
DOI: 10.1016/0022-3115(93)90207-F

A theory of swelling and gas release for reactor materials
journal, February 1964

Barnes, R. S.
Journal of Nuclear Materials, Vol. 11, Issue 2
DOI: 10.1016/0022-3115(64)90002-9

Development and Performance of Metal Fuel Elements for Fast Breeder Reactors
journal, May 1980

Walters, L. C.; Kittel, J. H.
Nuclear Technology, Vol. 48, Issue 3
DOI: 10.13182/NT80-A32473

Metallic fast reactor fuels
journal, January 1997

Hofman, G. L.; Walters, L. C.; Bauer, T. H.
Progress in Nuclear Energy, Vol. 31, Issue 1-2
DOI: 10.1016/0149-1970(96)00005-4

Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications
journal, June 2017

Zinkle, S. J.; Boutard, J. L.; Hoelzer, D. T.
Nuclear Fusion, Vol. 57, Issue 9
DOI: 10.1088/1741-4326/57/9/092005

Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure
journal, January 2000

Garner, F. A.; Toloczko, M. B.; Sencer, B. H.
Journal of Nuclear Materials, Vol. 276, Issue 1-3
DOI: 10.1016/S0022-3115(99)00225-1

Irradiation creep and embrittlement behavior of AISI 316 stainless steel at very high neutron fluences
journal, October 1988

Porter, D. L.; Garner, F. A.
Journal of Nuclear Materials, Vol. 159
DOI: 10.1016/0022-3115(88)90089-X

The Deformation and Ageing of Mild Steel: III Discussion of Results
journal, September 1951

Hall, E. O.
Proceedings of the Physical Society. Section B, Vol. 64, Issue 9
DOI: 10.1088/0370-1301/64/9/303

On the estimation of sink-absorption terms in reaction-rate-theory analysis of radiation damage
journal, July 1978

Nichols, F. A.
Journal of Nuclear Materials, Vol. 75, Issue 1
DOI: 10.1016/0022-3115(78)90026-0

Influence of particle dispersions on the high-temperature strength of ferritic alloys
journal, August 2007

Hoelzer, D. T.; Bentley, J.; Sokolov, M. A.
Journal of Nuclear Materials, Vol. 367-370, p. 166-172
DOI: 10.1016/j.jnucmat.2007.03.151

Mechanical properties of irradiated ODS-EUROFER and nanocluster strengthened 14YWT
journal, July 2009

McClintock, D. A.; Sokolov, M. A.; Hoelzer, D. T.
Journal of Nuclear Materials, Vol. 392, Issue 2
DOI: 10.1016/j.jnucmat.2009.03.024

Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part I—Mechanical and microstructural observations
journal, January 2013

Kim, Jeoung Han; Byun, Thak Sang; Hoelzer, David T.
Materials Science and Engineering: A, Vol. 559
DOI: 10.1016/j.msea.2012.08.042

Influence of processing on the microstructure and mechanical properties of 14YWT
journal, April 2016

Hoelzer, D. T.; Unocic, K. A.; Sokolov, M. A.
Journal of Nuclear Materials, Vol. 471
DOI: 10.1016/j.jnucmat.2015.12.011

Comparative Effect of Mo and Cr on Microstructure and Mechanical Properties in NbV-Microalloyed Bainitic Steels
journal, February 2018

Kostryzhev, Andrii; Singh, Navjeet; Chen, Liang
Metals, Vol. 8, Issue 2
DOI: 10.3390/met8020134

Development of Oxide Dispersion Strengthened Ferritic Steels for FBR Core Application, (I): Improvement of Mechanical Properties by Recrystallization Processing
journal, March 1997

Ukai, Shigeharu; Nishida, Toshio; Okada, Hirokazu
Journal of Nuclear Science and Technology, Vol. 34, Issue 3
DOI: 10.1080/18811248.1997.9733658

Present development status of EUROFER and ODS-EUROFER for application in blanket concepts
journal, November 2005

Lindau, R.; Möslang, A.; Rieth, M.
Fusion Engineering and Design, Vol. 75-79
DOI: 10.1016/j.fusengdes.2005.06.186

Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration
journal, August 2019

Massey, Caleb P.; Hoelzer, David T.; Seibert, Rachel L.
Journal of Nuclear Materials, Vol. 522
DOI: 10.1016/j.jnucmat.2019.05.019

Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part II—Mechanistic models and predictions
journal, January 2013

Kim, Jeoung Han; Byun, Thak Sang; Hoelzer, David T.
Materials Science and Engineering: A, Vol. 559
DOI: 10.1016/j.msea.2012.08.041

Thermal creep modeling of HT9 steel for fast reactor applications
journal, February 2011

Ryu, Ho Jin; Kim, Yeon Soo; Yacout, A. M.
Journal of Nuclear Materials, Vol. 409, Issue 3
DOI: 10.1016/j.jnucmat.2010.12.232

Creep deformation and fracture behavior of types 316 and 316L(N) stainless steels and their weld metals
journal, April 2000

Sasikala, G.; Mannan, S. L.; Mathew, M. D.
Metallurgical and Materials Transactions A, Vol. 31, Issue 4
DOI: 10.1007/s11661-000-0113-3

Mechanical Properties, Short Time Creep, and Fatigue of an Austenitic Steel
journal, April 2016

Brnic, Josip; Turkalj, Goran; Canadija, Marko
Materials, Vol. 9, Issue 4
DOI: 10.3390/ma9040298

Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys
journal, May 2005

Klueh, R. L.; Shingledecker, J. P.; Swindeman, R. W.
Journal of Nuclear Materials, Vol. 341, Issue 2-3
DOI: 10.1016/j.jnucmat.2005.01.017

Mechanical alloying — A perspective
journal, February 1990

Benjamin, John S.
Metal Powder Report, Vol. 45, Issue 2
DOI: 10.1016/S0026-0657(10)80124-9

The science and technology of mechanical alloying
journal, May 2001

Suryanarayana, C.; Ivanov, E.; Boldyrev, V. V.
Materials Science and Engineering: A, Vol. 304-306
DOI: 10.1016/S0921-5093(00)01465-9

High temperature fracture characteristics of a nanostructured ferritic alloy (NFA)
journal, December 2010

Byun, Thak Sang; Kim, Jeoung Han; Yoon, Ji Hyun
Journal of Nuclear Materials, Vol. 407, Issue 2
DOI: 10.1016/j.jnucmat.2010.09.031

Transient liquid phase bonding of ferritic oxide-dispersion-strengthened alloys
journal, February 2006

Krishnardula, Venu G.; Sofyan, Nofrijon I.; Gale, William F.
Metallurgical and Materials Transactions A, Vol. 37, Issue 2
DOI: 10.1007/s11661-006-0021-2

Diffusion bonding of 9Cr ODS ferritic/martensitic steel with a phase transformation
journal, October 2014

Noh, Sanghoon; Kimura, Akihiko; Kim, Tae Kyu
Fusion Engineering and Design, Vol. 89, Issue 7-8
DOI: 10.1016/j.fusengdes.2013.12.023

Pressure resistance welding of MA-957 to HT-9 for advanced reactor applications
journal, September 2018

Jerred, N. D.; Charit, I.; Zirker, L. R.
Journal of Nuclear Materials, Vol. 508
DOI: 10.1016/j.jnucmat.2018.05.046

The microstructure and strength properties of MA957 nanostructured ferritic alloy joints produced by friction stir and electro-spark deposition welding
journal, August 2007

Miao, P.; Odette, G. R.; Gould, J.
Journal of Nuclear Materials, Vol. 367-370, p. 1197-1202
DOI: 10.1016/j.jnucmat.2007.03.232

Effects of friction stir welding and post-weld annealing on nanostructured ferritic alloy
journal, April 2011

Etienne, A.; Cunningham, N. J.; Wu, Y.
Materials Science and Technology, Vol. 27, Issue 4
DOI: 10.1179/1743284710Y.0000000038

Joining of 14YWT and F82H by friction stir welding
journal, November 2013

Hoelzer, D. T.; Unocic, K. A.; Sokolov, M. A.
Journal of Nuclear Materials, Vol. 442, Issue 1-3
DOI: 10.1016/j.jnucmat.2013.04.027

Effect of friction stir welding and post-weld heat treatment on a nanostructured ferritic alloy
journal, February 2016

Mazumder, B.; Yu, X.; Edmondson, P. D.
Journal of Nuclear Materials, Vol. 469
DOI: 10.1016/j.jnucmat.2015.11.061

Economic benefits of advanced materials in nuclear power systems
journal, July 2009

Busby, J. T.
Journal of Nuclear Materials, Vol. 392, Issue 2
DOI: 10.1016/j.jnucmat.2009.03.018

Similar Records in DOE PAGES and OSTI.GOV collections:

Summary of Previous Mechanical Test Data on ODS Alloys 14YWT and OFRAC up to 1000ºC

Technical Report Hoelzer, David T.

The Nanostructured Ferritic Alloys (NFA) 14YWT and OFRAC were developed for future fission and fusion nuclear energy reactors requiring high-temperature mechanical properties that are tolerant to extreme neutron irradiation environments. The NFA contain a high concentration of Ti-, Y- and O-enriched nanoclusters (NC) and ultra-fine grains to achieve high temperature strength and creep properties and high sink strength for trapping irradiation induced point defects to minimize hardening and swelling and transmutated He atoms to form intragranular nano-size bubbles that prevent formation of coarse bubbles on grain boundaries that cause embrittlement. The mechanical properties of 14YWT and OFRAC have been acquiredmore »« less
https://doi.org/10.2172/1784108

Full Text Available
Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration

Journal Article Massey, Caleb P. ; Hoelzer, David T. ; Seibert, Rachel L. ; ... - Journal of Nuclear Materials

Fast reactor fuel cladding candidate materials require proficiency in extreme environments consisting of high temperatures and irradiation doses in excess of 150 displacements per atom (dpa). Nanostructured oxide dispersion strengthened (ODS) alloys have been developed extensively for this purpose due to their notable high temperature strength, creep resistance, and irradiation resistance. However, their properties can deteriorate if interstitial impurities such as C and N are not well controlled during the fabrication process. A new Fe-12Cr nanostructured ODS alloy OFRAC (Oak Ridge Fast Reactor Advanced Fuel Cladding) with solute additions of Mo, Ti, and Nb has been developed to provide themore »« less
Cited by 7
https://doi.org/10.1016/j.jnucmat.2019.05.019

Full Text Available
Bulk Nanostructured FCC Steels With Enhanced Radiation Tolerance

Technical Report Zhang, Xinghang ; Hartwig, K. Ted ; Allen, Todd ; ...

The objective of this project is to increase radiation tolerance in austenitic steels through optimization of grain size and grain boundary (GB) characteristics. The focus will be on nanocrystalline austenitic Fe-Cr-Ni alloys with an fcc crystal structure. The long-term goal is to design and develop bulk nanostructured austenitic steels with enhanced void swelling resistance and substantial ductility, and to enhance their creep resistance at elevated temperatures via GB engineering. The combination of grain refinement and grain boundary engineering approaches allows us to tailor the material strength, ductility, and resistance to swelling by 1) changing the sink strength for point defects,more »« less
https://doi.org/10.2172/1054231

Full Text Available
FY17 Status Report on the Micromechanical Finite Element Modeling of Creep Fracture of Grade 91 Steel

Technical Report Messner, M. C. ; Truster, T. J. ; Cochran, K. B. ; ...

Advanced reactors designed to operate at higher temperatures than current light water reactors require structural materials with high creep strength and creep-fatigue resistance to achieve long design lives. Grade 91 is a ferritic/martensitic steel designed for long creep life at elevated temperatures. It has been selected as a candidate material for sodium fast reactor intermediate heat exchangers and other advanced reactor structural components. This report focuses on the creep deformation and rupture life of Grade 91 steel. The time required to complete an experiment limits the availability of long-life creep data for Grade 91 and other structural materials. Design methodsmore »« less
https://doi.org/10.2172/1401966

Full Text Available
Optimization and testing results of Zr-bearing ferritic steels

Technical Report Tan, Lizhen ; Yang, Ying ; Tyburska-Puschel, Beata ; ...

The mission of the Nuclear Energy Enabling Technologies (NEET) program is to develop crosscutting technologies for nuclear energy applications. Advanced structural materials with superior performance at elevated temperatures are always desired for nuclear reactors, which can improve reactor economics, safety margins, and design flexibility. They benefit not only new reactors, including advanced light water reactors (LWRs) and fast reactors such as sodium-cooled fast reactor (SFR) that is primarily designed for management of high-level wastes, but also life extension of the existing fleet when component exchange is needed. Developing and utilizing the modern materials science tools (experimental, theoretical, and computational tools)more »« less
https://doi.org/10.2172/1159486

Full Text Available

Similar Records

Title: Modern nanostructured ferritic alloys: A compelling and viable choice for sodium fast reactor fuel cladding applications

Abstract

Citation Formats

Structural materials challenges for advanced reactor systems journal, March 2009

Sodium fast reactor evaluation: Core materials journal, July 2009

Structural materials for fission & fusion energy journal, November 2009

Materials challenges in nuclear energy journal, February 2013

French and United Kingdom Experience of High-Burnup Mixed-Oxide Fuel in Sodium-Cooled Fast Breeder Reactors journal, January 2008

Structural materials for next generation nuclear systems: Challenges and the path forward journal, December 2015

Motivation for utilizing new high-performance advanced materials in nuclear energy systems journal, December 2016

A Once-Through Fuel Cycle for Fast Reactors journal, July 2010

Ferritic/martensitic steels for next-generation reactors journal, September 2007

An overview of neutron irradiation effects in LMFBR materials journal, July 1982

Austenitic stainless steels with improved resistance to radiation-induced swelling journal, April 1976

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

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

A US perspective on fast reactor fuel fabrication technology and experience part I: metal fuels and assembly design journal, June 2009

Metal fuel test program in the FFTF journal, September 1993

Metallic fuels for advanced reactors journal, July 2009

Status of LMR fuel development in the United States of America journal, September 1993

A US perspective on fast reactor fuel fabrication technology and experience. Part II: Ceramic fuels journal, August 2009

History of fast reactor fuel development journal, September 1993

Experience with advanced driver fuels in EBR-II journal, September 1993

A theory of swelling and gas release for reactor materials journal, February 1964

Development and Performance of Metal Fuel Elements for Fast Breeder Reactors journal, May 1980

Metallic fast reactor fuels journal, January 1997

Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications journal, June 2017

Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure journal, January 2000

Irradiation creep and embrittlement behavior of AISI 316 stainless steel at very high neutron fluences journal, October 1988

The Deformation and Ageing of Mild Steel: III Discussion of Results journal, September 1951

On the estimation of sink-absorption terms in reaction-rate-theory analysis of radiation damage journal, July 1978

Influence of particle dispersions on the high-temperature strength of ferritic alloys journal, August 2007

Mechanical properties of irradiated ODS-EUROFER and nanocluster strengthened 14YWT journal, July 2009

Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part I—Mechanical and microstructural observations journal, January 2013

Influence of processing on the microstructure and mechanical properties of 14YWT journal, April 2016

Comparative Effect of Mo and Cr on Microstructure and Mechanical Properties in NbV-Microalloyed Bainitic Steels journal, February 2018

Development of Oxide Dispersion Strengthened Ferritic Steels for FBR Core Application, (I): Improvement of Mechanical Properties by Recrystallization Processing journal, March 1997

Present development status of EUROFER and ODS-EUROFER for application in blanket concepts journal, November 2005

Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration journal, August 2019

Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part II—Mechanistic models and predictions journal, January 2013

Thermal creep modeling of HT9 steel for fast reactor applications journal, February 2011

Creep deformation and fracture behavior of types 316 and 316L(N) stainless steels and their weld metals journal, April 2000

Mechanical Properties, Short Time Creep, and Fatigue of an Austenitic Steel journal, April 2016

Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys journal, May 2005

Mechanical alloying — A perspective journal, February 1990

The science and technology of mechanical alloying journal, May 2001

High temperature fracture characteristics of a nanostructured ferritic alloy (NFA) journal, December 2010

Transient liquid phase bonding of ferritic oxide-dispersion-strengthened alloys journal, February 2006

Diffusion bonding of 9Cr ODS ferritic/martensitic steel with a phase transformation journal, October 2014

Pressure resistance welding of MA-957 to HT-9 for advanced reactor applications journal, September 2018

The microstructure and strength properties of MA957 nanostructured ferritic alloy joints produced by friction stir and electro-spark deposition welding journal, August 2007

Effects of friction stir welding and post-weld annealing on nanostructured ferritic alloy journal, April 2011

Joining of 14YWT and F82H by friction stir welding journal, November 2013

Effect of friction stir welding and post-weld heat treatment on a nanostructured ferritic alloy journal, February 2016

Economic benefits of advanced materials in nuclear power systems journal, July 2009

Structural materials challenges for advanced reactor systems
journal, March 2009

Sodium fast reactor evaluation: Core materials
journal, July 2009

Structural materials for fission & fusion energy
journal, November 2009

Materials challenges in nuclear energy
journal, February 2013

French and United Kingdom Experience of High-Burnup Mixed-Oxide Fuel in Sodium-Cooled Fast Breeder Reactors
journal, January 2008

Structural materials for next generation nuclear systems: Challenges and the path forward
journal, December 2015

Motivation for utilizing new high-performance advanced materials in nuclear energy systems
journal, December 2016

A Once-Through Fuel Cycle for Fast Reactors
journal, July 2010

Ferritic/martensitic steels for next-generation reactors
journal, September 2007

An overview of neutron irradiation effects in LMFBR materials
journal, July 1982

Austenitic stainless steels with improved resistance to radiation-induced swelling
journal, April 1976

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

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

A US perspective on fast reactor fuel fabrication technology and experience part I: metal fuels and assembly design
journal, June 2009

Metal fuel test program in the FFTF
journal, September 1993

Metallic fuels for advanced reactors
journal, July 2009

Status of LMR fuel development in the United States of America
journal, September 1993

A US perspective on fast reactor fuel fabrication technology and experience. Part II: Ceramic fuels
journal, August 2009

History of fast reactor fuel development
journal, September 1993

Experience with advanced driver fuels in EBR-II
journal, September 1993

A theory of swelling and gas release for reactor materials
journal, February 1964

Development and Performance of Metal Fuel Elements for Fast Breeder Reactors
journal, May 1980

Metallic fast reactor fuels
journal, January 1997

Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications
journal, June 2017

Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure
journal, January 2000

Irradiation creep and embrittlement behavior of AISI 316 stainless steel at very high neutron fluences
journal, October 1988

The Deformation and Ageing of Mild Steel: III Discussion of Results
journal, September 1951

On the estimation of sink-absorption terms in reaction-rate-theory analysis of radiation damage
journal, July 1978

Influence of particle dispersions on the high-temperature strength of ferritic alloys
journal, August 2007

Mechanical properties of irradiated ODS-EUROFER and nanocluster strengthened 14YWT
journal, July 2009

Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part I—Mechanical and microstructural observations
journal, January 2013

Influence of processing on the microstructure and mechanical properties of 14YWT
journal, April 2016

Comparative Effect of Mo and Cr on Microstructure and Mechanical Properties in NbV-Microalloyed Bainitic Steels
journal, February 2018

Development of Oxide Dispersion Strengthened Ferritic Steels for FBR Core Application, (I): Improvement of Mechanical Properties by Recrystallization Processing
journal, March 1997

Present development status of EUROFER and ODS-EUROFER for application in blanket concepts
journal, November 2005

Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration
journal, August 2019

Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part II—Mechanistic models and predictions
journal, January 2013

Thermal creep modeling of HT9 steel for fast reactor applications
journal, February 2011

Creep deformation and fracture behavior of types 316 and 316L(N) stainless steels and their weld metals
journal, April 2000

Mechanical Properties, Short Time Creep, and Fatigue of an Austenitic Steel
journal, April 2016

Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys
journal, May 2005

Mechanical alloying — A perspective
journal, February 1990

The science and technology of mechanical alloying
journal, May 2001

High temperature fracture characteristics of a nanostructured ferritic alloy (NFA)
journal, December 2010

Transient liquid phase bonding of ferritic oxide-dispersion-strengthened alloys
journal, February 2006

Diffusion bonding of 9Cr ODS ferritic/martensitic steel with a phase transformation
journal, October 2014

Pressure resistance welding of MA-957 to HT-9 for advanced reactor applications
journal, September 2018

The microstructure and strength properties of MA957 nanostructured ferritic alloy joints produced by friction stir and electro-spark deposition welding
journal, August 2007

Effects of friction stir welding and post-weld annealing on nanostructured ferritic alloy
journal, April 2011

Joining of 14YWT and F82H by friction stir welding
journal, November 2013

Effect of friction stir welding and post-weld heat treatment on a nanostructured ferritic alloy
journal, February 2016

Economic benefits of advanced materials in nuclear power systems
journal, July 2009