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Aaron Craft Craft Dr. Aaron E. Craft is a research scientist at Idaho National Laboratory, the principal investigator for various projects to develop advanced neutron imaging and other capabilities for post-irradiation examination of nuclear fuel. He has helped develop portable digital x-ray radiography and computed tomography systems for in-field investigation of munitions. Additionally, his expertise with x-ray micro computed tomography has aided multiple programs at INL to develop advanced nuclear fuels and other energy-related materials. He received his doctorate in nuclear science and engineering from Colorado School of Mines, and his bachelor’s and master’s in nuclear engineering from Missouri University of Science and Technology. Outside of work, he enjoys teaching students at local schools about nuclear energy.<div class="ExternalClassE5835D5750594433994B3D88A18C8B37"><p>​Ph.D., Nuclear Science and Engineering - Colorado School of Mines</p><p>M.S., Nuclear Engineering - Missouri S&T</p><p>B.S., Nuclear Engineering - Missouri S&T</p></div><div class="ExternalClassAEB3F9896A254D6CAB30D010845AA0DF"><div><p><span aria-hidden="true"></span>Dr. Craft’s research interests include non-destructive examinations of irradiated nuclear fuels, with an emphasis on x-ray and neutron radiography and tomography techniques. His current projects are focused on developing advanced digital neutron imaging systems capable of imaging highly-radioactive objects with a longer-term goal of making neutron computed tomography a routine technique for post-irradiation examination. Dr. Craft is also leading the formation of a Beamline Examinations for Applied Material Science (BEAMS) Workgroup that will develop x-ray and neutron diffraction and scattering techniques in addition to traditional imaging capabilities. Dr. Craft is also a Nuclear Engineer who enjoys nearly everything nuclear and has contributed to a wide variety of nuclear R&D projects beyond post-irradiation examination.</p></div></div><div class="ExternalClass802C39D958214D639991918929854FA6"><p><span style="font-family:"baskerville old face", serif;font-size:11.5pt;"><font color="#000000">Center for Space Nuclear Research Fellow </font></span></p><p><span style="font-family:"baskerville old face", serif;font-size:11.5pt;">NEUP Fellow</span></p><div class="ExternalClassAE85084A4DE34413A940617B9842486D"><p><span aria-hidden="true"></span><span aria-hidden="true"></span>​American Society for Nondestructive Testing (ASNT)</p><p>American Society for Testing and Materials (ASTM)</p><p>American Nuclear Society (local Chapter President at CSM)</p><p><span aria-hidden="true"></span>ORNL Neutron Beam Sciences Review Committee</p><p>Missouri S&T Nuclear Engineering Department Advising Committee<span aria-hidden="true"></span></p></div></div><div class="ExternalClass0B391E8B3A2C4E3785B54F8532205FF9"><p><strong>Publications (Primary Author) </strong></p><p>Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory, 2015. Physics Procedia, 69, 483-490.</p><p><br>Submersion criticality safety of a tungsten-rhenium urania cermet fuel for space propulsion and power applications, 2014. Nuclear Engineering and Design, 273, 143-149.</p><p><br>Design, construction, and demonstration of the Colorado School of Mines neutron imaging facility, 2013. Nuclear Technology, 184(2), 198-209. <br>Installation of a new neutron beam facility at the USGS TRIGA reactor, 2014. Nuclear Technology, 185(1), 85-99.</p><p><br>Submersion criticality safety analysis of a tungsten-based fuel for nuclear power and propulsion applications, 2012. GLEX-2012, International Astronautical Federation, Paris, France.</p><p><br>Construction and installation of the Colorado School of Mines neutron imaging facility, 2012. American Nuclear Society, 106, 555-558.</p><p><br>Unreviewed safety question analysis for the new neutron imaging facility at the USGS TRIGA reactor, 2012. American Nuclear Society, 106, 95-99. </p><p><br>Development of a neutron radiography and tomography facility at the Colorado School of Mines, 2011. American Nuclear Society, 104, 225-226.</p><p><br>Reactivity control schemes for fast spectrum space nuclear reactors, 2011. Nuclear Engineering and Design, 241, 1516-1528.</p><p><br>Advanced shield development for a fission surface power system for the lunar surface, 2011. Aerospace Engineering, Institution of Mechanical Engineers, Part G, 225(2), 204-212. </p><p><br>Radiation shielding options for a nuclear reactor power system landed on the lunar surface, 2010. Nuclear Technology, 172, 255-272.</p><p><br>Development of a nuclear-powered fully-mobile outpost for the lunar outpost, 2009. NETS-2009, 203537, Atlanta, GA.</p><p><br>Axial radiation shielding for the affordable fission surface power system, 2009. NETS-2009, 203630, Atlanta, GA.</p><p><br>Radiation shielding options for the affordable fission surface power system, 2009. SPESIF-2009, Huntsville, AL, AIP Proceedings, 1103, 466-477.</p><p><br>Reactivity control schemes for fast-spectrum space nuclear reactors, 2008. STAIF-2008, Melville, NY, ed. M. S. El-Genk, AIP Conference Proceedings, 969, 326-336.</p><p> </p><p><strong>Publications (Joint Author) </strong></p><p>Ultra-high resolution digital detector for neutron Imaging with efficient gamma discrimination, 2015. IEEE Nuclear Science Symposium.</p><p> <br>Evaluating quantitative 3D image analysis as a design tool for low enriched uranium fuel compacts for the transient reactor, Nuclear Materials, 2015. submitted for publication.</p><p><br>Coordinating space nuclear research advancement and education, 2009. ANS Winter Meeting, INL/CON-09-16278. </p></div>Nuclear;Nuclear Engineering;Nuclear Fuels Scientist
Andrew Smolinski Smolinski<div class="ExternalClass65D2D864B2444D378E6BE4FB6B23B780"><p>​M.S. Nuclear Engineering and Engineering Physics, University of Wisconsin – Madison, 2002</p><p>B.S. Nuclear Engineering, University of Wisconsin – Madison, 2002</p></div><div class="ExternalClass075650A07FB04DC4B26E06ABB99D34C9"><ul><li>Reactor Physics Testing</li><li>In-core Experimentation</li><li>Neutron Imaging</li><li>Neutron Diffraction</li><li>Reactor Instrumentation and Control Systems</li></ul></div><div class="ExternalClass135E176628BF4229B896D16ECE9F893B"><p>​National Organization of Test, Research, and Training Reactors (TRTR)</p></div><div class="ExternalClass92B66DBBA8244615A33D983BDAB3620D"><p><em>1.</em>      <em>Neutron Radiography of Irradiated Nuclear Fuel at Idaho National Laboratory</em></p><p>Author(s): Craft, Aaron E.; Wachs, Daniel M.; Okuniewski, Maria A.; et al.</p><p>Source: Proceedings of the 10th World Conference on Neutron Radiography (Wcnr-10) Volume: 69 Pages: 483-490 Published: 2015 </p><p> </p><p><em>2.</em>      <em>Evaluation of Neutron Radiography Reactor LEU-Core Start-Up Measurements</em></p><p>Author(s): Bess, John D.; Maddock, Thomas L.; Smolinski, Andrew T.; et al.</p><p>Source: Nuclear Science and Engineering Volume: 178 Issue: 4 Pages: 550-561 Published: DEC 2014 </p><p> </p><p><em>3.</em>      <em>The Impact of Water Saturation in Graphite Reflector Blocks on NRAD Benchmark Simulation</em></p><p>Author(s): Bess, J.D.; Smolinski, A.T.</p><p>Source: Transactions of the American Nuclear Society Volume: 110 Pages: 638-40 Published: 2014</p></div>Nuclear Engineering;Nuclear;Neutron/ion irradiation damage of nuclear materials Systems Engineer/Nuclear Facility Manager
Glen Papaioannou Papaioannou<div class="ExternalClassEF3A468B9382419B867714044064A38C"><p>​Bachelors, Mechanical Engineering, University of New Haven CT, 2005</p><p>Associates, Mechanical Engineering Technology, Waterbury State Technical College CT, 1992</p><p>Associates, Business Marketing, Becker Junior College MA, 1989</p></div><div class="ExternalClassE86D92BBFE6F44C58267B28186F20E17"><p>​Neutron Radiography; real time digital imaging of nuclear fuel, computed tomography, resolution improvements, quantitative data analysis from images, standards development</p></div><div class="ExternalClassB9915D5E99FD49698C9599176AB3B17D"><p>American Society for Nondestructive Testing, ASNT</p><p>American Society for Testing and Materials, ASTM</p><p>International Society of Automation, ISA</p></div><div class="ExternalClass792976385BFC4141A626C3DAF5703E47"><p>Journal:  Nuclear Engineering and Technology, Corresponding Author:  Aaron Craft</p><p>Co-Authors:  Bruce A Hilton, Ph.D.; Glen C Papaioannou</p><p>Title:  Characterization of a Neutron Beam Following Reconfiguration of the Neutron Radiography Reactor (NRAD) Core and Addition of New Fuel Element, 5/19/2015</p><p>Journal: ScienceDirect, PhysicsProcedia, Volume 69, 2015, Pages 483-490, Proceedings of the 10th World Conference on Neutron Radiography (WCNR-10) Grindelwald, Switzerland October 5–10, 2014, Corresponding Author:  Aaron Craft, Co-Authors: Daniel M. Wachs, Maria A. Okuniewski, David L. Chichester, Walter J. Williams, Glen C. Papaioannou, Andrew T. Smolinski, Title: Neutron Radiography of Irradiated Nuclear Fuel at Idaho National Laboratory, 9/10/2015</p></div>Nuclear Fuels;Nuclear;Neutron diffraction and imaging;Materials Science and Engineering;Process/Operations Engineering;Image processing algorithm development;Data collection;Neutron/ion irradiation damage of nuclear materials<div class="ExternalClassE8A3F7AADA324D6A8F3A2891CF8157C0"><p>​ORCID: 0000-0003-3912-0328</p></div>Instrument Engineer, Registered Professional Engineer, Certified Level II Neutron Radiographer, Beamline Examinations for Applied Material Science
Katelyn Wheeler Wheeler<div class="ExternalClassE218F3AA0CA34278B5D9E49A79BC4EAA"><p>​B. S. Nuclear Engineering, Idaho State University, 2012</p></div><div class="ExternalClass1D4DF418D84A4B4186886979E3B12E56"><p>​Eddy Current Examinations, Gamma Spectroscopy, and mechanical testing</p></div><div class="ExternalClass599D9765900841888E1FB489E1F36F7B"><p>​Idaho ANS member</p></div><div class="ExternalClass11AF950FA95341E88F681EB8FDF508D1"><p>​"Oxidation, Embrittlement, and Growth of TREAT Zircaloy-3 Cladding", Nuclear Material Performance </p></div>Nuclear Engineering;Nuclear Fuels;Mechanical Testing Engineer
David Sell Sell<div class="ExternalClassBE72D69FFC244DA086DE33072848E05F"><p>​B.S. Mechanical Engineering, University of Pittsburgh, 1986</p></div><div class="ExternalClass12AC09DC3EA249358446690BDBBB62AA"><p>​Registered Professional Engineer (Idaho)</p></div><div class="ExternalClass0B3EA4D3709E4872832C732787597883"><ol><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">D.A. Sell, C.E. Baily, T.J. Malewitz, P.G. Medvedev, D.L. Porter, B.A. Hilton, "Hot Cell System for Determining Fission Gas Retention in Metallic Fuels", HOTLAB 2016 Conference, Karlsruhe, Germany, October 2016 </div></li><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">B.R. Westphal, K.J. Bateman, and D.A. Sell, "Pyro-In-Situ Measurement of Pu Content in U/TRU Ingots", Idaho National Laboratory, February 2014</div></li><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">Co-Author, "Evaluation of Analytical Results Following Laboratory Scale Feasibility Study Voloxidation", 2012 International Pyroprocessing Research Conference, Fontana, WI, August 2012</div></li><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">Co-Author, "Investigation of Decladding Via Oxidation for MOX Fast Reactor Fuel", International Pyroprocesing Research, Jeju, Republic of Korea, August 2008</div></li><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">Co-Author, "Direct Assay of Filter Media Following DEOX Testing", ANS Global 2007, Boise, ID, September 2007</div></li><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">Co-Author, "Effect of Process Variables During the Head-end Treatment of Spent Oxide Fuel", International Pyroprocessing Research Conference, Idaho Falls, ID August 2006</div></li><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">D.A. Sell and D. Fisher, "Mobile Melt-Dilute Technology Development Project FY 2005 Test Report", Idaho National Laboratory and Savannah National Laboratory, January 2005</div></li><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">Co-Author, "Mobile Melt-Dilute Technology Development Project Summary Report on Results of Experiment & Tests to Support MMD Furnace & Canister/Crucible System Design" September 2004</div></li><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">Lead Author, "Mobile Melt-Dilute Technology Development Prototype Canister/Crucible Design", September 2004</div></li><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">Co-Author, "Evaporative Removal of Bond Sodium from Low Burn-Up Blanket Fuel, ANS 2004 Winter Meeting " November 2004</div></li><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">Lead Author, "The Development of Mobile Melt-Dilute Technology for the Treatment of Former Soviet Union Research Reactor Fuel", 12TH International Conference on Nuclear Engineering (ICONE-12), Arlington, Virginia, April 2004</div></li><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">Co-Author, "MEDEC Treatment of FERMI-1 Sodium-Bond Blanket Fuel in Preparation for Final Geological Disposal", A Life-Cycle Cost Estimate and Feasibility Report, March 2003</div></li><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">Co-Author, ANS Technical Conference Paper:  "The Design and Installation of a Cesium Trap for <br>BN-350", June 2003</div></li><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">Co-Author, "MEDEC Treatment of FERMI-1 Sodium-Bond Blanket Fuel in Preparation for Final Geological Disposal", Final Technical Report, August 2003</div></li><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">Co-Author, "The Development of Mobile Melt-Dilute Technology for the Treatment of Former Soviet Union Research Reactor Fuel", ANS GLOBAL 2003 Conference, October 2003</div></li><li><div class="ExternalClass99E0371E14DD45C18D212E513CCC2293">K.L. Toews, S.D. Herrmann, D.A. Sell, R.H. Rigg, R.G. Pahl,   "Application of the MEDEC Process to Treat Fermi-1 Sodium-Bonded Spent Nuclear Fuel", DOE Spent Fuel and Fissile Materials Management Conference, Charleston, South Carolina, September 2002.</div></li></ol></div>Nuclear Fuels;Nuclear Engineering HFEF Hot Cell PIE Equipment Engineer
Cad Christensen Christensen<div class="ExternalClass8471FF6983EB4C48938635D97AFC7280"><p>A.A.S., Diesel Power Generation Technology, Idaho State University, 2001</p><p>B.S., Industrial Engineering, University of Idaho, 2012</p></div>Nuclear remote systems engineer