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Robert O'Brienhttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=707Robert O'Brien<div class="ExternalClass6C3C694DB7964FDC9AC7A515E570AC85"><p>Masters degree in Physics with Space Science and Technology, University of Leicester, 2006</p><p>PhD in Physics Research, University of Leicester, 2010</p></div><div class="ExternalClassF916CF1713B24AF29B0BB5ED27A162A3"><p>​Commercial, Space & Defense Nuclear Systems and Fuels Engineering for light water reactors, micro-reactors, Nuclear Thermal Propulsion and Radioisotope Power Systems. Development of advanced nuclear fuel and radioisotope source fabrication technologies including Spark Plasma Sintering and Laser Additive manufacturing. Research to industrial scale-up of manufacturing processes. Nuclear fuel irradiation performance and safety testing. Nuclear instrumentation design and development. Direct energy and high power laser systems development.</p></div><div class="ExternalClass507BE29638F34802B66E6507B70D3037"><p>Fellow of the Royal Astronomical Society, 2008</p><p>American Nuclear Society, 2011</p></div><div class="ExternalClassC78D067A7BE447AE8BBA6EC78F949EC0"><ol style="list-style-type:decimal;"><li><span style="font-size:13pt;">R.C. O'Brien "Porous Nuclear Fuel Formed by Additive Manufacturing, Nuclear Reactor Materials and Related Methods" BA-991 Patent Number 2939-P14093US.</span></li><li><span style="font-size:13pt;">H. Chu, R.C. O'Brien, M.P. Bakas, S.K. Cook "Large Scale Plasma Sintering of Silicon Carbide Plate" BA-799 Patent Application - No. 2939-P13215US.</span></li><li><span style="font-size:13pt;">W. Roger Cannon, Rita E. Hoggan, Arnold Erickson, Bryan Forsmann, Robert C. O'Brien &</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">Paul A. Lessing "Controlled relative humidity storage for high toughness and strength of</span></p><p style="text-align:justify;"><span style="font-size:13pt;">binderless green pellets", Journal of the American Ceramics Society, (2017) DOI:</span></p><p style="text-align:justify;"><span style="font-size:13pt;">10.1111/jace.14982.</span></p><ol start="4" style="list-style-type:decimal;"><li><span style="font-size:13pt;">R.C. O'Brien, N.D. Jerred, "Spark Plasma Sintering of W-UO2 cermets". Journal of Nuclear</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">Materials. 433 (2013) 50-54.</span></p><ol start="5" style="list-style-type:decimal;"><li><span style="font-size:13pt;">R.C. O'Brien, et al., "Spark Plasma Sintering of simulated radioisotope materials in tungsten</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">cermets". Journal of Nuclear Materials. 393 (2009) 108-113.DOI:</span></p><p style="text-align:justify;"><span style="font-size:13pt;">10.1016/j.jnucmat.2009.05.012.</span></p><ol start="6" style="list-style-type:decimal;"><li><span style="font-size:13pt;">R. C. O'Brien, et al., "Resumption of Transient Testing at the Idaho National Laboratory Treat</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">Reactor: Development of Experimental and Analytical Capabilities in Support of the Accident</span></p><p style="text-align:justify;"><span style="font-size:13pt;">Tolerant Fuels Campaign." Proceedings of OECD/NEA Workshop on Pellet-Cladding Interaction (PCI) in Water-Cooled Reactors, June 22-24, Lucca, Italy.</span></p><ol start="7" style="list-style-type:decimal;"><li><span style="font-size:13pt;">N.E. Woolstenhulme, J.D. Bess, C.B. Davis, G.K. Housley, C.B. Jensen, R.C. O'Brien, and D.M.</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">Wachs, "TREAT Irradiation Vehicle Designs, Capabilities, And Future Plans", Proceedings of</span></p><p style="text-align:justify;"><span style="font-size:13pt;">the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1 – 5, 2016.</span></p><ol start="8" style="list-style-type:decimal;"><li><span style="font-size:13pt;">O'Brien, R.C.; Wachs, D.M.; Beasley, A.A. "ATF-3: an overview of the accident tolerant fuels</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">transient testing campaign in the TREAT reactor" Transactions of the American Nuclear Society,</span></p><p style="text-align:justify;"><span style="font-size:13pt;">Volume 112 (2015) Pages: 355-357.</span></p><ol start="9" style="list-style-type:decimal;"><li><span style="font-size:13pt;">Woolstenhulme, N.E.; Baker, C.C.; Bess, J.D.; Davis, C.B.; Housley, G.K.; Jensen, C.B.;</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">O'Brien, R.C.; Snow, S.D. "TREAT experiment vehicle design and future plans" Transactions of</span></p><p style="text-align:justify;"><span style="font-size:13pt;">the American Nuclear Society Volume 112 (2015) Pages: 369-71.</span></p><ol start="10" style="list-style-type:decimal;"><li><span style="font-size:13pt;">R.C. O'Brien "CSNR-Aerojet Rocketdyne Cermet Fuels Research: Summary & status",</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">Proceedings of the 2015 Nuclear and Emerging Technologies for Space (NETS 2015) conference,</span></p><p style="text-align:justify;"><span style="font-size:13pt;">Albuquerque, NM.</span></p><ol start="11" style="list-style-type:decimal;"><li><span style="font-size:13pt;">A.E. Craft, R.C. O'Brien, , S.D. Howe, , J.C. King, "Submersion criticality safety of tungstenrhenium</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">urania cermet fuel for space propulsion and power applications" Journal of Nuclear</span></p><p style="text-align:justify;"><span style="font-size:13pt;">Engineering and Design Volume 273 (2014) Pages 143–149</span></p><ol start="12" style="list-style-type:decimal;"><li><span style="font-size:13pt;">Xiaoyu Zhang, James E. O'Brien, Robert C. O'Brien, Joseph J. Hartvigsen, Greg Tao, Gregory K.</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">Housley, "Improved durability of SOEC stacks for high temperature electrolysis", International</span></p><p style="text-align:justify;"><span style="font-size:13pt;">Journal of Hydrogen Energy, Volume 38, Issue 1, 11 January 2013, Pages 20–28.</span></p><ol start="13" style="list-style-type:decimal;"><li><span style="font-size:13pt;">Xiaoyu Zhang, James E. O'Brien, Robert C. O'Brien, Gregory K. Housley, "Durability evaluation</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">of reversible solid oxide cells" Journal of Power Sources, Volume 242, (2013) Pages 566–574.</span></p><ol start="14" style="list-style-type:decimal;"><li><span style="font-size:13pt;">R.C. O'Brien, "Development of a Radiological Spark Plasma Sintering Facility". Proceedings of:</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">Nuclear and Emerging Technologies for Space (NETS-2013), 2013; Albuquerque, NM, USA.</span></p><ol start="15" style="list-style-type:decimal;"><li><span style="font-size:13pt;">O'Brien, R.C. ; O'Brien, J. E.; Stoots, C. M.; Zhang, X.; Farmer, S. C.; Cable, T. L.; Setlock, J.</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">A., "TESTING AND PERFORMANCE ANALYSIS OF NASA 5 CM BY 5 CM BISUPPORTED</span></p><p style="text-align:justify;"><span style="font-size:13pt;">SOLID OXIDE ELECTROLYSIS CELLS OPERATED IN BOTH FUEL CELL</span></p><p style="text-align:justify;"><span style="font-size:13pt;">AND STEAM ELECTROLYSIS MODES" Journal article: PROCEEDINGS OF THE ASME</span></p><p style="text-align:justify;"><span style="font-size:13pt;">INTERNATIONAL MECHANICAL ENGINEERING CONGRESS AND EXPOSITION, 2011,</span></p><p style="text-align:justify;"><span style="font-size:13pt;">VOL 4, PTS A AND B Pages: 513-521 Published: 2012.</span></p><ol start="16" style="list-style-type:decimal;"><li><span style="font-size:13pt;">R.C. O'Brien and J.A. Katalenich, "Mixed Americium-Curium Heat Sources for Radioisotope</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">Heaters and Power Systems", Journal of Propulsion and Power, Vol. 27, No. 5 (2011), pp. 1131-</span></p><p style="text-align:justify;"><span style="font-size:13pt;">1134.</span></p><p style="text-align:justify;"> </p><p style="text-align:justify;"> </p><ol start="17" style="list-style-type:decimal;"><li><span style="font-size:13pt;">H.R. Williams, J.C. Bridges, R.M. Ambrosi, M.-C. Perkinson, J. Reed, L. Peacocke, N.P.</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">Bannister, S.D. Howe, R.C. O'Brien, A.C. Klein "Mars reconnaissance lander: Vehicle and</span></p><p style="text-align:justify;"><span style="font-size:13pt;">mission design", Journal of Planetary and Space Science Volume 59, Issue 13 ( 2011) Pages</span></p><p style="text-align:justify;"><span style="font-size:13pt;">1621–1631.</span></p><ol start="18" style="list-style-type:decimal;"><li><span style="font-size:13pt;">Steven D. Howe, Robert C. O'Brien, Richard M. Ambrosi, Brian Gross, Jeff Katalenich, Logan</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">Sailer, Mark McKay, John C. Bridges, Nigel P. Bannister, "The Mars Hopper: an impulse driven,</span></p><p style="text-align:justify;"><span style="font-size:13pt;">long range, long-lived mobile platform utilizing in-situ Martian resources" Acta Astronautica</span></p><p style="text-align:justify;"><span style="font-size:13pt;">Volume 69, Issues 11–12(2011) Pages 1050–1056.</span></p><ol start="19" style="list-style-type:decimal;"><li><span style="font-size:13pt;">S.D. Howe, R.C. O'Brien R.M. Ambrosi, et al "The Mars Hopper: an impulse-driven, long-range,</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">long-lived mobile platform utilizing in situ Martian resources", Journal of Aerospace Engineering</span></p><p style="text-align:justify;"><span style="font-size:13pt;">Part G, Volume: 225 Issue: G2 Pages: 144-153 Special Issue: SI (2011).</span></p><ol start="20" style="list-style-type:decimal;"><li><span style="font-size:13pt;">M.S. Skidmore, R.M. Ambrosi, and R.C. O'Brien, "Neutron sources for in-situ planetary science</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">applications". Journal of Nuclear Materials. 608 (2009) 403-409.DOI:</span></p><p style="text-align:justify;"><span style="font-size:13pt;">10.1016/j.nima.2009.07.011.</span></p><ol start="21" style="list-style-type:decimal;"><li><span style="font-size:13pt;">R.C. O'Brien, et al., Fabrication of prismatic fuel elements for space power and nuclear thermal</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">propulsion reactors by spark plasma sintering". Proceedings of: Nuclear and Emerging Technologies for Space (NETS 2009), Paper Number 206153; June 14‐19, 2009; Atlanta,GA.</span></p><ol start="22" style="list-style-type:decimal;"><li><span style="font-size:13pt;">R.C. O'Brien, et al., "Production of safe radioisotope heat sources by Spark Plasma Sintering".</span></li></ol><p style="text-align:justify;"><span style="font-size:13pt;">Proceedings of: Nuclear and Emerging Technologies for Space (NETS-2009), Paper Number</span></p><p style="text-align:justify;"><span style="font-size:13pt;">206155; June 14-19, 2009; Atlanta, GA</span></p></div>Advanced Manufacturing and Intelligent Systemshttps://bios.inl.gov/BioPhotos/RobertOBrien.jpgGroup Leader for Advanced Manufacturing, New Fuel Systems and Feedstock Development Principal investigator for TREAT experiments
Timothy Hydehttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=314Timothy HydeTimothy A. Hyde is the Fuel Fabrication and Nuclear Material Management division director at the INL’s Materials and Fuels Complex (MFC). This division is responsible for nuclear facility management of four facilities including two Haz Cat II facilities. The division also has the responsibility to develop new fuel fabrication processes and to fabricate and assemble numerous irradiation experiments. Hyde has bachelor’s and master’s degrees in mechanical engineering. In more than 25 years of research and management, he has worked in a wide range of technical disciplines, including ceramic and metal alloy fuel development, membrane permeability testing, plasma disassociation of hydrocarbons to grow carbon nano-tubes, aerosol particle measurement, magnetic properties measurement, magnetic alloy development and numerous experimental and mechanical design projects<div class="ExternalClass7C4C03ECFAF84595B67CE66B6E1BB871"><p>Bachelor’s and master’s degrees in mechanical engineering</p><br></div>Nuclear;Nuclear Fuels;Nuclear Nonproliferation and Nuclear Forensicshttps://bios.inl.gov/BioPhotos/Tim_Hyde.jpgDirector of Fuel Fabrication and Nuclear Material Management
Randall Fieldinghttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=455Randall FieldingMr. Fielding has worked in the area of metallic and transmutation fuel fabrication development for over 15 years, including sodium cooled and gas cooled reactor fuel systems. His areas of expertise include metallic fuel casting, extrusion, non-destructive evaluation analysis, and experiment assembly. In addition to fuel manufacturing development, Mr. Fielding has participated in design and review of proposed fabrication facilities.<div class="ExternalClassB15518C3F2A14BF6918F028C658ACCB1"><p>​ M.S. Materials Science and Engineering, University of Idaho, 2006</p></div><div class="ExternalClassC05CF1AED6B34885BB243A502BDC928C"><p>​Metallic and ceramic fuel fabrication, casting and forming technologies, welding, and irradiation experiment assembly</p></div>Nuclear Fuels;Materials Science and Engineeringhttps://bios.inl.gov/BioPhotos/RandallFielding.jpgMetal Fuel Development Group Lead
Connor Woolumhttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=708Connor Woolum<div class="ExternalClassEBDD3582B05F4FD3889338DD881132EF"><p>BS Nuclear Engineering, Texas A&M University, May 2013</p><p>MS Nuclear Engineering (with materials science emphasis), Texas A&M University, December 2014</p></div><div class="ExternalClass95A46996213548E8A2522881960171AD"><ul><li><p>Novel and unique fuel forms, with a focus on accident tolerant fuels</p></li><li><p>Novel and unique cladding materials</p></li></ul><br></div><div class="ExternalClass6781DC23A4C8448FBD3593B7152E6A15"><p>​American Nuclear Society</p></div>Nuclear Fuels;Nuclear Engineering;Nuclear;Materials Science and Engineeringhttps://bios.inl.gov/BioPhotos/ConnorWoolum.jpgFuel development engineer
Corey Shannonhttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=709Corey ShannonCorey Shannon started working at Idaho National Laboratory in 2009 as a nuclear facility operator. Since then, he has held multiple roles including: certified fissionable material handler for the Fuel Manufacturing Facility, glovebox and process equipment operator, material balance area custodian, secure facilities training staff specialist, criticality safety officer, and system engineer for the Hot Fuels Examination Facility (HFEF). While supporting HFEF, Corey was involved with the first hot cell window replacement and Safety Analysis Report (SAR) implementation. In Corey’s current role, he provides engineering and operations support for the special nuclear material program. Prior to working at INL, Corey worked for Halliburton Energy Services as a wireline and perforating field professional. This work included using electro-mechanical and nuclear tools to measure, record, and analyze petro-physical properties in gas and oil well bores. While at Halliburton, Corey was also the assistant local radiation safety officer.<div class="ExternalClassC70857F9F64549CF8E40D68A5CABE091"><p>​B.S. in Mechanical Engineering, Idaho State University, 2005</p></div><div class="ExternalClass34269A18B213448FACE31D0AFB89D971"><p>​American Glovebox Society (AGS) Member</p></div>https://bios.inl.gov/BioPhotos/CoreyShannon.JPGNuclear research facility engineer
Steven Herrmannhttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=456Steven Herrmann<div class="ExternalClassFC3B1FDA52C843DFB4D0D666301A63EA"><p>BS Chemical Engineering, Brigham Young University, 1990</p><p>Masters of Business Administration, Idaho State University, 1997</p><p>PhD Chemical Engineering, University of Idaho, currently enrolled<br></p><p><br></p></div><div class="ExternalClass22AC3034189145D99270E18BFF621800"><p>As an INL employee for over 20 years, Steven Herrmann has gained experience in research, design, development, and demonstration of processes and equipment. He also has managed projects and personnel in the treatment of various materials of interest for the U.S. Department of Energy (DOE), including spent nuclear fuel and associated high-level, transuranic, and low-level wastes. These activities have primarily involved pyrochemical and electrochemical techniques and processes to separate and recover actinides from spent nuclear fuel, while directing fission and activation products into appropriate waste forms for disposal. Steven is currently leading a demonstration of an integrated kg-scale pyroprocess at INL for used nuclear fuel as part of a Joint Fuel Cycle Studies program – a 10-yr Cooperative Research and Development Agreement between multiple DOE national laboratories, the Republic of Korea, and the International Atomic Energy Agency.</p></div><div class="ExternalClass1EC21A9E49944727BE1484652BD0AA96"><p>Licensed Professional Engineer, Nuclear Engineering</p><p>Licensed Professional Engineer, Chemical Engineering</p><p>Member of the American Nuclear Society</p><p>Member of the American Institute of Chemical Engineers</p><p>Member of TMS<br></p><p><br></p></div><div class="ExternalClass4AC53962A3F8409F88FF52697D29B684"><ol><li>Steven D. Herrmann, Shelly X. Li, Brian R. Westphal, "Separation and Recovery of Uranium and Group Actinide Products from Irradiated Fast Reactor MOX Fuel via Electrolytic Reduction and Electrorefining," <em>Separation Science and Technology</em>, 47, 2044, 2012.</li><li>S. Phongikaroon, S. D. Herrmann, M. F. Simpson, "Diffusion Model for Electrolytic Reduction of Uranium Oxides in a Molten LiCl-Li<sub>2</sub>O Salt," <em>Nuclear Technology</em>, 174 (1), 85, April 2011.</li><li>S. D. Herrmann and S. X. Li, "Separation and Recovery of Uranium Metal from Spent Light Water Reactor Fuel via Electrolytic Reduction and Electrorefining," <em>Nuclear Technology</em>, 171 (3), 252, September 2010.</li><li>Shelly X. Li, Steven D. Herrmann, Michael F. Simpson, "Electrochemical Analysis of Actinides and Rare Earth Constituents in Liquid Cadmium Cathode Product from Spent Fuel Electrorefining," <em>Nuclear Technology</em>, 171 (3), 292, September 2010.</li><li>Shelly X. Li, S. D. Herrmann, K. M. Goff, M. F. Simpson, R. W. Benedict, "Actinide Recovery Experiments with Bench-Scale Liquid Cadmium Cathode in Real Fission Product-Laden Molten Salt," <em>Nuclear Technology</em>, 165 (2), 190, February 2009.</li><li>Michael F. Simpson, Steven D. Herrmann, "Modeling the Pyrochemical Reduction of Spent UO<sub>2</sub> Fuel in a Pilot-Scale Reactor," <em>Nuclear Technology</em>, 162 (2), 179, May 2008.</li><li>Steven Herrmann, Shelly Li, Michael Simpson, "Electrolytic Reduction of Spent Light Water Reactor Fuel – Bench-Scale Experiment Results," <em>Journal of Nuclear Science and Technology</em>, 44 (3), 361, 2007.</li><li>Supathorn Phongikaroon, Steven D. Herrmann, Shelly X. Li, Michael F. Simpson, "Measurement and Analysis of Gas Bubbles near a Reference Electrode in Aqueous Solutions," <em>Industrial & Engineering Chemistry Research</em>, 45 (22), 7679, 2006.</li><li>S. D. Herrmann, S. X. Li, M. F. Simpson, S. Phongikaroon, "Electrolytic Reduction of Spent Nuclear Oxide Fuel as Part of an Integral Process to Separate and Recover Actinides from Fission Products," <em>Separation Science and Technology</em>, 41 (10), 1965, 2006.</li><li>S. X. Li, S. D. Herrmann, "Experimental Observations of a Thoria Oxygen Sensor in a Molten Salt System," <em>Journal of the Electrochemical Society</em>, 149 (2), H39, 2002.<br></li></ol><p><br></p></div>Fuel Recycling;Electrochemical engineeringhttps://bios.inl.gov/BioPhotos/StevenHerrmann.jpgResearcher
Zachary Rowehttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=458Zachary Rowe<div class="ExternalClass1F2268BB3C294B648378881C26283B17"><div><p>Bachelor of Science, Organizational Leadership and Performance, Idaho State University, 2017</p></div></div><div class="ExternalClass7F991BEA45514131A11BC535D56A1516"><p>​Discover, demonstrate and secure innovative nuclear energy solutions, clean energy and critical infrastructure. </p></div><div class="ExternalClass8E51E84F6E664812A291F4E7D8DEB5DC"><p>​<span style="line-height:115%;font-family:"times new roman",serif;font-size:12pt;"><font color="#000000">Idaho American Nuclear Society (IANS)</font></span></p></div>Nuclear Fuels;Nuclear Engineering;Nuclearhttps://bios.inl.gov/BioPhotos/ZacharyRowe.jpgExperimental Fuels Facility (EFF), Fuels and Applied Science Building (FASB), and Manufacturing Development Laboratory (MDL) Nuclear Facility Manager/Shift Supervisor
Leah Squireshttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=427Leah Squires<div class="ExternalClass83EF9EA83E2B4203ADD286726E2A3515"><p>​PhD in Chemistry, University of Illinois at Urbana-Champaign, 2007<br> BS in Chemistry, University of Cincinnati, 2002</p></div><div class="ExternalClassCD7AE476859F4666948006135C51A609"><p>​<span style="line-height:115%;font-family:verdana, sans-serif;font-size:10pt;"><font color="#000000">Isolation and purification of actinide metals, including neptunium and americium, for use in the fabrication of transmutation fuels.<span>  </span></font><font color="#000000">These metals are currently available only as oxides or in metal mixtures, not as pure metals. Processes must be continually designed and developed to isolate them from the various metal and oxide mixes and to reduce the oxides to metals.</font></span></p></div><div class="ExternalClassD76E2AB978E54958BB0C32D5B25CEB3A"><p><strong>Squires, LN</strong>; King, J; Fielding, R; Lessing,P. <em>Isolation of High Purity Americium Metal via Distillation</em> J. Nucl. Mater., 500 (2018), pp. 26-32.</p><p> </p><p><strong>Squires, LN</strong>; Lessing, P.  <em>Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride </em> J. Nucl. Mater., 471 (2016), pp. 65-68.</p><p> </p><p>Burkes, Douglas E.; Kennedy, Rory; Hartmann, Thomas; <strong>Squires, Leah N</strong>. <em>Phase Characteristics of a U-30Pu-5Am-3Np-20Zr Metallic Alloy Containing Rare Earths</em>. Journal of Phase Equilibria and Diffusion (2009), 30(4), 309-317.</p><p> </p><p>Goldcamp, Michael J.; Edison, Sara E.; <strong>Squires, Leah N</strong>.; Rosa, Dell T.; Vowels, Neil K.; Coker, Nathan L.; Bauer, Jeanette A. Krause; Baldwin, Michael J.  <em>Structural and Spectroscopic Studies of Nickel(II) Complexes with a Library of Bis(oxime)amine-Containing Ligands</em>.  Inorganic Chemistry  (2003), 42(3), 717-728.  </p></div>Analytical Chemistryhttps://bios.inl.gov/BioPhotos/LeahSquires.jpgScientist
Scott Wildehttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=429Scott WildeMr. Scott Wilde has been with INL (formerly Argonne National Laboratory-West) since 1977, a span of forty-plus years. Mr. Wilde has worked in many positions of increasing responsibility over his years at the INL. Scott has focused his energies on hands-on research with nuclear fuels and materials specializing in gloveboxes, hot cells, inert atmosphere systems, and, finally, financial planning and scheduling for the Advanced Fuels Campaign. Mr. Wilde started out as a senior engineering technician at the Hot Fuels Examination Facility from 1977-1984. There he became an expert at manipulator use, shielded cask work, radioactive shipments, cranes and special nuclear material handling equipment. Then Scott moved to Safeguards and Security work until 1998. In that capacity, Scott ensured compliance with regulations dealing with receipt, storage, and transfer of nuclear material within and outside of INL. He was also involved with tracking and storage of precious metals, source materials, packaging of radioactive materials. From 1998-2007, Scott worked as a Senior Scientific Technician. In this position, Scott learned and was responsible for maintaining all aspects of the Analytical Laboratory (AL). These included facility instrumentation, scientific equipment, gloveboxes and hot cells. Mr. Wilde also served as the MBA custodian and precious metals custodian for the AL. In this role, Scott was responsible for ensuring the accounting for all SNM and precious metals in the AL. From 2007-2011, Mr. Wilde served as shift supervisor in the AL. Scott managed a team of technicians and was responsible for overseeing of the equipment, work within the facility, support organization’s interaction with the facility, and coordinating and ensuring the technical work done in the facility was represented on the plan of the week. Mr. Wilde continued to perform the MBA custodian responsibilities. Currently, Mr. Wilde currently serves as an expeditor for the fuel fabrication and characterization department at MFC. In this job, Scott interfaces with the fuels group project managers and facility personnel to expedite and facilitate research work on projects to meet DOE and INL milestones. In addition, Scott serves as the point of contact between the tenant and operations and maintenance organization to provide resources to correct facility deficiencies to meet deliverables. Mr. Wilde has trained on P-6 planning and scheduling software to help with the scheduling and financially tracking of work packages within the program. He works with project managers to input the scope and budgets for each work package into PICS and tracked the progress of those work accounts throughout the year.Analytical Chemistry;Nuclear Fuels;Nuclearhttps://bios.inl.gov/BioPhotos/ScottWilde.jpgExpeditor for the fuel fabrication and characterization department: facilitate research work to meet DOE and INL milestones Scheduler - schedules and financially tracks work packages
Curtis Clarkhttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=443Curtis Clark<div class="ExternalClass9B745508FD68429EAA7957B047957B6A"><p>​Masters in Metallurgical Engineering, University of Idaho, 1999</p></div><div class="ExternalClassF7593C4B82A04DA2BE3AECB4C962A6FE"><p>​Monolithic fuel fabrication methods<br> Metal fuel powder atomization</p></div>Nuclearhttps://bios.inl.gov/BioPhotos/CurtisClark.jpgDepartment Manager
Cory Browerhttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=444Cory Brower Mr. Cory S. Brower is the nuclear facility manager for the Fuel Manufacturing Facility at Idaho National Laboratory's Materials and Fuels Complex. This facility is responsible for fuel fabrication and testing of metal and oxide nuclear fuel for the advancement of new fuels technology, disposition of legacy nuclear materials, testing of nuclear material detection equipment for homeland security and the safe storage of fuels to be used for research and development. Mr. Brower has in-depth experience managing and operating spent nuclear fuel facilities including transportation of fuel shipments both foreign and domestic. Mr. Brower brings 28 years of experience in operating, maintaining and managing nuclear facilities. Nuclearhttps://bios.inl.gov/BioPhotos/CoryBrower.JPGNuclear Facility Manager
Larry Evenshttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=446Larry Evens<div class="ExternalClassF377741B77204A57861CF6B0E746E100"><p>​<span style="line-height:115%;font-family:"calibri",sans-serif;font-size:11pt;"><font color="#000000">B.S. Business Management/Marketing,</font><span><font color="#000000"> </font></span><font color="#000000">1990</font></span></p></div><div class="ExternalClassB812B1F1F6264E20BD7EA8386FF6E41A"><p><span style="line-height:115%;font-family:"calibri",sans-serif;font-size:11pt;"><font color="#000000">Facility Management relating to research needs and mission support for the Idaho National Laboratory.</font></span></p></div>Nuclearhttps://bios.inl.gov/BioPhotos/larryevens.JPGNuclear Facility Manager