Personal information

Material sciences and beyond!
United States

Biography

Dr. Busby is the Division Director for the Materials Science and Technology Division in the Physical Sciences Directorate at Oak Ridge National Laboratory. His contributions range from light water reactors to sodium reactors and space reactor systems as well as research in support of the ITER project.

Dr. Busby’s research is focused on materials performance and development of materials for nuclear reactor applications. While at ORNL, Dr. Busby has participated in materials research efforts for space reactors, fusion machines, advanced fast reactors, and light water reactors. Ultimately, the results of this diverse research will enable the development of operating criteria for structural materials in a variety of adverse environments that will allow for design and operation of safe, reliable, and cost-effective nuclear systems.

Previously, Dr. Busby led the Materials Aging and Degradation Pathway for the DOE –Office of Nuclear Energy Light Water Reactor Sustainability Research and Development program.

He also led the Nuclear Energy Enabling Technologies Materials Cross-cut effort, in addition to participation in several nuclear industry-sponsored research tasks.

As principal investigator for the DOE Office of Science ITER Program, he led an investigation into the feasibility of utilizing an innovative cast austenitic stainless steel (SS) for the first wall structure of the international ITER project. The ORNL team utilized advanced computational thermodynamics modeling to successfully devise a cast SS within the internationally approved chemical composition limits for the ITER stainless steel with a tensile strength comparable to wrought stainless steel (>50% improvement in strength over the cast stainless steel previously developed by industry), without compromising other properties. In 2010, Dr. Busby received the Presidential Early Career Award for Science and Engineering, following this effort for “excellence in research leading to the development of high performance cast stainless steels, a critical part of the U.S. Contributions to ITER project, and for his mentoring of students both as an Adjunct Assistant Professor at the University of Michigan and at ORNL.”

Activities

Employment (1)

Oak Ridge National Laboratory: Oak Ridge, TN, US

Division Director (Material Sciences and Technology)
Employment
Source: Self-asserted source
Jeremy Busby

Works (50 of 107)

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Technical Gap Assessment for Materials and Component Integrity Issues for Molten Salt Reactors

2019-03-01 | Report
Contributors: Jeremy Busby; Lauren Garrison; Lianshan Lin; Stephen Raiman; Sam Sham; Chinthaka Silva; Hong Wang; R. Iyengar; G. Tartal
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Technologies to Reactors: Enabling Accelerated Deployment of Nuclear Energy Systems Workshop Report

2018-12-12 | Report
Contributors: Kenneth Tobin Jr; Jeremy Busby; Micah Hackett; Lonnie Love; Sudarsanam Babu; Lei Cao; W David Pointer; William Wharton; A Qualls; Benjamin Betzler
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Crossref

Integrated Modeling of Second Phase Precipitation in Cold-Worked 316 Stainless Steels under Irradiation

Acta Materialia
2017 | Journal article
Source: Self-asserted source
Jeremy Busby

Accelerating post-irradiation examination with latest-generation electron microscopy hardware and software

2016 | Book
Source: Self-asserted source
Jeremy Busby

Microstructural Evolution of Type 304 and 316 Stainless Steels under Neutron Irradiation at LWR Relevant Conditions

Journal of the Minerals Metals & Materials Society (JOM)
2016 | Journal article
Source: Self-asserted source
Jeremy Busby

Roles of Vacancy/Interstitial Diffusion and Segregation in the Microchemistry at Grain Boundaries of Irradiated Fe-Cr-Ni alloys

Journal of Nuclear Materials
2016 | Journal article
Source: Self-asserted source
Jeremy Busby

Thermal Aging Phenomena in Cast Duplex Stainless Steels

Journal of the Minerals Metals & Materials Society (JOM)
2016 | Journal article
Source: Self-asserted source
Jeremy Busby

Analysis of Stress Corrosion Cracking in Alloy 718 Following Commercial Reactor Exposure

Journal of Nuclear Materials
2015 | Journal article
Source: Self-asserted source
Jeremy Busby

Characterization of Materials Properties and Crack Propagation Mechanisms in Damaged Alloy 718 Leaf Springs Following Commercial Reactor Exposure

2015 | Book
Source: Self-asserted source
Jeremy Busby

Defect Sink Characteristics of Specific Grain Boundary Types in 304 Stainless Steels Under High Dose Neutron Environments

Acta Materialia
2015 | Journal article
Source: Self-asserted source
Jeremy Busby

DEFORMATION LOCALIZATION AND DISLOCATION CHANNEL DYNAMICS IN NEUTRON IRRADIATED AUSTENITIC STAINLESS STEELS

Journal of Nuclear Materials
2015 | Journal article
Source: Self-asserted source
Jeremy Busby

Development of a robust modeling tool for radiation-induced segregation in austenitic stainless steels

2015 | Report
Source: Self-asserted source
Jeremy Busby

Formulating the strength factor alpha for improved predictability of radiation hardening

Journal of Nuclear Materials
2015 | Journal article
Source: Self-asserted source
Jeremy Busby

LAMDA: A facility for advanced characterization of irradiated materials at Oak Ridge National Laboratory

2015 | Book
Source: Self-asserted source
Jeremy Busby

Presentation on oxide characterization collaboration with India

2015 | Book
Source: Self-asserted source
Jeremy Busby

Radiation Damage In Reactor Cavity Concrete

2015 | Book
ISBN:

0335-5004

Source: Self-asserted source
Jeremy Busby

Stability of precipitate phases in Fe-rich Fe-Cr-Ni-Mo alloys

Metallurgical and Materials Transactions A
2015 | Journal article
Source: Self-asserted source
Jeremy Busby

Tensile and toughness assessment of the procured advanced alloys

2015 | Report
Source: Self-asserted source
Jeremy Busby

Thermal aging modeling and validation on the Mo containing Fe-Cr-Ni alloys

2015 | Report
Source: Self-asserted source
Jeremy Busby

Alloying and Grain Boundary Structure Effects on the Radiation Induced Segregation Response in Type 304 Variants Under Neutron Irradiation

2014 | Book
Source: Self-asserted source
Jeremy Busby

Analysis of phase transformation studies in solute addition alloys

2014 | Report
Source: Self-asserted source
Jeremy Busby

Effect of thermal aging on precipitation kinetics of gamma prime in alloy 617

Journal of Phase Equilibria and Diffusion
2014 | Journal article
Source: Self-asserted source
Jeremy Busby

INITIAL RESULTS ON THE CORRELATION BETWEEN LOCALIZED DEFORMATION AND IRRADIATION-ASSISTED STRESS CORROSION CRACKING RESPONSE USING BEND TESTS

2014 | Report
Source: Self-asserted source
Jeremy Busby

Materials Aging and Degradation Research to Support Long-Term Operation Decisions

2014 | Book
Source: Self-asserted source
Jeremy Busby

Microstructural Characterization of Deformation Localization at Small Strains in a Neutron Irradiated 304 Stainless Steel

Journal of Nuclear Materials
2014 | Journal article
Source: Self-asserted source
Jeremy Busby

Microstructure and Basic Mechanical Properties of the Procured Advanced Alloys for the Advanced Radiation Resistant Materials Program

2014 | Report
Source: Self-asserted source
Jeremy Busby

Post Irradiation Examination of Alloy 718 Microstructure and Mechanicl Properties Following Commercial Reactor Exposure

2014 | Book
Source: Self-asserted source
Jeremy Busby

ROLE OF SCALE FACTOR DURING TENSILE TESTING OF SMALL SPECIMENS

2014 | Book
Source: Self-asserted source
Jeremy Busby

Strengthening of Irradiation-Induced Defects in AISI 304 and 316 Variants

2014 | Book
Source: Self-asserted source
Jeremy Busby

Thermodynamic modeling and Kinetics Simulation of Precipitate Phases in AISI 316 Stainless Steels

Journal of Nuclear Materials
2014 | Journal article
Source: Self-asserted source
Jeremy Busby

A Multilength Scale Approach to Characterizing Localized Deformation in Irradaited Specimens

2013 | Book
Source: Self-asserted source
Jeremy Busby

Alloying effect of Ni and Cr on irradiated microstructural evolution of type 304 stainless steels

Journal of Nuclear Materials
2013 | Journal article
Source: Self-asserted source
Jeremy Busby

Computational modeling on the precipitate phases in Austenitic steels

2013 | Book
Source: Self-asserted source
Jeremy Busby

Concrete Aging and Degradation in NPPs: LWRs Program R&D Progress Report

2013 | Book
Source: Self-asserted source
Jeremy Busby

Concrete Aging and Degradation in NPPs: LWRS Program R&D Progress Report

2013 | Book
Source: Self-asserted source
Jeremy Busby

Dependence on grain boundary structure of radiation induced segregation in a 9 wt.% Cr model ferritic/martensitic steel

Journal of Nuclear Materials
2013 | Journal article
Source: Self-asserted source
Jeremy Busby

Effect of Ni and Cr alloying on microstructural evolution of BOR60-irradiated type 304 stainless steels

2013 | Book
Source: Self-asserted source
Jeremy Busby

Effect of Thermomechanical Treatment on 9Cr Ferritic-Martensitic Steels

Journal of Nuclear Materials
2013 | Journal article
Source: Self-asserted source
Jeremy Busby

Experimental and modeling results of creep–fatigue life of Inconel 617 and Haynes 230 at 850 °C

Journal of Nuclear Materials
2013 | Journal article
Source: Self-asserted source
Jeremy Busby

Grain Boundary Engineering for Structure Materials of Nuclear Reactors

Journal of Nuclear Materials
2013 | Journal article
Source: Self-asserted source
Jeremy Busby

LWRS Program - Updates of High-Fluence Induced Microstructural Evolution of Austenitic Stainless Steels under LWR Relevant Conditions

2013 | Report
Source: Self-asserted source
Jeremy Busby

Microstructural Evolution of Type 304 Variants and 316 Stainless Steels under Neutron Irradiation

2013 | Book
Source: Self-asserted source
Jeremy Busby

Overview of DOE-NE LWRS Materials Aging and Degradation Pathway

2013 | Book
Source: Self-asserted source
Jeremy Busby

Thermodynamic Modeling and Experimental Study of the Fe-Cr-Zr System

Journal of Nuclear Materials
2013 | Journal article
Source: Self-asserted source
Jeremy Busby

Thermodynamic modeling and kinetics simulation of precipitate phases in Austenitic steels

2013 | Book
Source: Self-asserted source
Jeremy Busby

Thermomechanical treatment for improved neutron irradiation resistance of austenitic alloy (Fe-21Cr-32Ni)

Journal of Nuclear Materials
2013 | Journal article
Source: Self-asserted source
Jeremy Busby

Twinning and martensitic transformations in nickel-enriched 304 austenitic steel during tensile and indentation deformations

Materials Science and Engineering A
2013 | Journal article
Source: Self-asserted source
Jeremy Busby

Analytical description of true stress-true strain curves for neutron-irradiated stainless austenitic steels

Journal of Nuclear Materials
2012 | Journal article
Source: Self-asserted source
Jeremy Busby

Development of High-Performance Structural Alloys for Nuclear Energy Systems

2012 | Book
Source: Self-asserted source
Jeremy Busby

Formation of Magnetic Phase in Irradiated Model Austenitic Alloys

2012 | Book
Source: Self-asserted source
Jeremy Busby
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