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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
Cynthia Adkins Adkins<div class="ExternalClass6977F33097474ADCAB914C5A7D2CC5A5"><p>M.S., Materials Science and Engineering, University of Florida, 2012</p><p>M.S., Engineering Management, Robert Morris University, 2006</p><p>B.S., Chemistry, Penn State University, 1995</p></div><div class="ExternalClassC7A936BC89A745F98AF8AA376C507FF1"><p>Techniques used to characterize the relationship between microstructure and thermal conductivity of transuranic materials used for reactor fuel.  Particularly using differential scanning calorimetry techniques for measurement of phase transformation temperatures and pulse laser flash as well as photo reflectance methods to measure thermal conductivity on the 100 micron scale.  </p><p>Study of metallic fuel systems including thermal properties and microstructure with the goal to increase the basic science knowledge of mechanisms for thermal conductivity and thermodynamic behavior. </p></div><div class="ExternalClass33CA00E872C84DBBAD2069F781782FA6"><p>​American Nuclear Society member 2007 to present, Executive Committee Member, Materials Science and Technologies Division, 2012 to present</p><p>TMS: The Minerals, Metals, Materials Society, member 2012 to present</p><p>North American Thermal Analysis Society member, 1996 to 2006</p></div><div class="ExternalClass742C7E8980D24902AB6EC46E80558FF1"><ol><li>Aitkaliyeva, A., <strong>Papesch, Cynthia A</strong>,, "TEM Identification of Subsurface Phases in Ternary U-Pu-Zr Fuel", Journal of Nuclear Materials, vol. 473, May 2016, pp. 75-82.</li><li>Aitkaliyeva, A., <strong>Papesch, Cynthia A</strong>,, "TEM Examination of Phases Formed Between U-Pu-Zr Fuel and Fe", Journal of Nuclear Materials, vol. 467, part 2, December 2015, pp. 717-723</li><li>Aitkaliyeva, A., <strong>Papesch,</strong><strong> </strong><strong>Cynthia</strong><strong> </strong><strong>A</strong>,, "Characterization of Phases formed between U-Pu-Mo alloys and Fe-12Cr Cladding", Journal of Nuclear Materials, vol. 464, September 2014, pp. 28-35</li><li>Moore, Donald T., <strong>Papesch,</strong><strong> </strong><strong>Cynthia</strong><strong> </strong><strong>A</strong>. (co-author), "In-Pile Irradiation Induced Defects and the Effect on Thermal Diffusivity of MgO", Journal of Nuclear Materials, vol. 434, no. 1-3, March 2013, pp. 90-96</li><li>Burkes, Douglas E., <strong>Papesch,</strong><strong> </strong><strong>Cynthia</strong><strong> </strong><strong>A</strong>. (co-author), "Thermo-physical Properties of DU-10 wt.% Mo Alloys", Journal of Nuclear Materials, vol. 403, no. 1-3, August 2010, pp. 160-166</li><li>Burkes, Douglas E., <strong>Papesch,</strong><strong> </strong><strong>Cynthia</strong><strong> </strong><strong>A</strong>. (co-author), "Phase Characteristics of a Number ofU-Pu-Am-Np-Zr Metallic Alloys for Use as Fast Reactor Fuels", Journal of Nuclear Materials, vol. 396, no. 1, January 2010, pp. 49-56</li><li>Burkes, Douglas, E., <strong>Papesch,</strong><strong> </strong><strong>Cynthia</strong><strong> </strong><strong>A</strong>. (co-author), "Phase Characteristics of a U-20Pu-3Am-2Np-15Zr Metallic Alloy Containing Rare Earths", Journal of Alloys and Compounds, vol. 239, no. 12, December 2009, pp. 2747-2753</li></ol></div>Nuclear;Nuclear Fuels;Materials Science and Engineering;Thermophysical Properties of Nuclear Fuel Materials Scientist – Thermal Properties
Karen Wright Wright Karen Wright is the Instrument Scientist for the EPMA at the Materials and Fuels Complex at Idaho National Laboratory, which she joined in 2000. She set up and operated a JEOL 8900 electron probe microanalyzer for use in studying environmental samples such as radiologically contaminated sediments and asbestiform minerals. More recently, she set up and operated a Cameca SX100R shielded electron probe microanalyzer for the purpose of analyzing irradiated nuclear fuels. In addition to analysis, she has been involved in the construction of transuranic standards and the design of remotely-handled standards and other equipment. Karen holds a master’s degree in geological science. Karen initiated a session for the analysis of irradiated materials at the Microscopy and Microanalysis annual conference and has chaired it. She also served as membership chair for the Microanalysis Society for three years. She recently worked as a visiting scientist at the Institute for Transuranium Elements in Karlsruhe, Germany. In addition to work with microanalysis, Karen has developed radiological decontamination methods, for which she holds two patents and won an R&D100 award.<div class="ExternalClassD2E8D0349A6F4D55BC1E16FAC7C42ABD"><p><strong><span style="color:#000000;font-family:calibri;font-size:11pt;font-style:normal;font-variant:normal;font-weight:400;text-decoration:none;vertical-align:baseline;white-space:pre-wrap;background-color:transparent;">Master of Science in Geological Science, Idaho State University, 1998</span></strong></p></div><div class="ExternalClass95E9F3CC573742E985C36CC097C291FF"><ul><li><div><p>​Electron probe microanalysis of irradiated nuclear fuels to include metal, oxide, and TRISO type fuels</p></div></li><li><p>Development of primary and secondary check standards to increase the accuracy of EPMA analysis of irradiated fuels</p></li><li><p>Developing and testing radiological decontamination methods</p></li></ul></div><div class="ExternalClass604CDCD96F164122889828F03405CA54"><p>Member of the Microanalysis Society</p><p>Member of the European Microanalysis Society</p></div><div class="ExternalClass34DEF07F4250491A97CA30D7C61773B8"><p><strong>Wright, K.E.</strong>, Popa, K., Poeml, P., 2017, Synthesis and characterization of PuPO4--a potential analytical standard for EPMA actinide quantification, accepted for publication in the journal, "IOP Conference Series: Materials Science and Engineering" (in press)</p><p><strong>Wright, K.E.</strong>, Van Rooyen I.J., 2016, Electron Probe Microanalysis of Irradiated and 1600<sup>o</sup>C Safety-Tested AGR-1 TRISO Fuel Particles with Low and High Retained <sup>110m</sup>Ag, 2016 ANS Winter Meeting and Nuclear Technology Expo, Las Vegas, Nevada</p><p><strong>Wright, K.E</strong>., Van Rooyen, I. J., 2016, Fission Product Distribution in Irradiated TRISO Fuel, Microscopy and Microanalysis, 22 (S3), 1490-1491</p></div>Advanced Characterization;Nuclear Fuels Scientist
Mukesh Bachhav Bachhav<div class="ExternalClassE689035C760F403BBC55476E70FCEA10"><p>​<span style="line-height:115%;font-family:"times new roman",serif;font-size:12pt;"><font color="#000000">Ph.D, Materials Science, University of Rouen, France, 2012.<span>                                                              </span></font></span></p><p><span style="line-height:115%;font-family:"times new roman",serif;font-size:12pt;"><font color="#000000"></font><font color="#000000">Masters, Physics, University of Pune, India, 2007</font><span><font color="#000000">   </font></span></span></p></div><div class="ExternalClassD5CEB5B3F9FA4C62A23096A1653A5B73"><p>​<span style="background:#fefefe;color:#333333;line-height:115%;font-family:"times new roman",serif;font-size:12pt;">Research focuses on understanding and quantifying the mechanisms controlling microstructural evolution in alloy systems, nuclear fuels, interfacial properties, and irradiation effects in materials. </span></p></div><div class="ExternalClassEBFA4BB1549A4D51962FF66B220F5389"><p>​<span style="line-height:115%;font-family:"times new roman",serif;font-size:12pt;"><font color="#000000">Member of International Youth Nuclear Congress.<span>                                                                </span></font></span></p><p><span style="line-height:115%;font-family:"times new roman",serif;font-size:12pt;"><font color="#000000"></font><font color="#000000">Recognized reviewer for Journal of applied physics, Applied surface science, Microscopy and Microanalysis, Journal of Physics D: Applied Physics, Applied Physics Letters, Material Science and Engineering B, Journal of Nuclear materials. </font></span></p></div><div class="ExternalClass67D98025FC9F49F1875A893897F407A6"><p>​</p><p>1)     <a><span style="text-decoration:underline;">α′ precipitation in neutron-irradiated Fe–Cr alloys</span></a></p><p>M Bachhav, GR Odette, EA Marquis</p><p>2)     <a><span style="text-decoration:underline;">Microstructural changes in a neutron-irradiated Fe–15at.% Cr alloy</span></a>                                          M Bachhav, GR Odette, EA Marquis</p><p>3)     <a><span style="text-decoration:underline;">Microstructure and Chemistry of Electrodeposited Mg Films</span></a>                                                     MN Bachhav, NT Hahn, KR Zavadil, EG Nelson, AJ Crowe, BM Bartlett,  PW Chu, VJ, Araullo-Peters, EA Marquis</p><p>4)     <a><span style="text-decoration:underline;">Evidence of lateral heat transfer during laser assisted atom probe tomography analysis of large band gap materials</span></a>                                                                                                                   MN Bachhav, R Danoix, F Vurpillot, B Hannoyer, SB Ogale, F Danoix</p><p>5)     Investigation of O-18 enriched hematite (α-Fe2O3) by laser assisted atom probe tomography                                                                                                                                     M Bachhav, F Danoix, B Hannoyer, JM Bassat, R Danoix</p></div>Advanced Characterization;Nuclear Fuels;Materials Characterization;Materials Properties and Performance scientist
Fidelma Di Lemma Di Lemma<div class="ExternalClass1423F59C934046D794C4D524662322BE"><p>​B.S degrees, Nuclear Engineering, L'Universita' di Roma "La Sapienza", 2009. </p><p>Masters degrees, Nuclear Engineering, L'Universita' di Roma "La Sapienza", 2011</p><p>Ph.D. Applied Sciences, Tu Delft, 2015</p></div><div class="ExternalClass623D0B3E632844CA941A7250F6A6ABC0"><p>​International Youth Nuclear Congress Acting as Research Chair for innovation and grants committee secretary </p></div><div class="ExternalClassAF5AC341456C4BA4B6DC544D738E567E"><p>Di Lemma et al. "RADES an experimental set-up for the characterization of aerosol release from nuclear and radioactive materials", Journal of Aerosol Science, 70, 2014, 36-49.</p><p>Di Lemma et al., "Fission product partitioning in aerosol release from simulated spent nuclear fuel", Journal of Nuclear Materials, 465, 2015, 127-134.</p><p>Di Lemma "Experimental investigation of the influence of Mo contained in stainless steel on Cs chemisorption behavior", Journal of Nuclear Materials, 484, 2017, 174-182.</p><p>Full list available on</p></div>Advanced Characterization;Nuclear Engineering Scientist/Metallography 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
Daniel Jadernas Jadernas Daniel Jadernas is an R&D Scientist at Idaho National Laboratory’s Materials and Fuel Complex. Working at the Irradiated Materials Characterization Laboratory, Daniel is the focused ion beam (FIB) Instrument Group Leader. He is responsible for research activities that utilize FIBs and the development of novel techniques for characterizing materials. Daniel has 13 years of experience using electron and ion optical techniques in conjunction with related analytical techniques (EDS, WDS, EBSD, EELS, etc.) in both academic and industrial settings with a focus on nuclear materials. Daniel graduated with a Master of Science in Physics from the University of Linkoping, Sweden. After that, he spent three years performing academic research at University of Linkoping before transitioning to Studsvik Nuclear AB where he worked for eight years in both managerial and specialist roles with post-irradiation examinations of commercial reactor fuel and fuel components. Daniel has authored more than forty scientific papers and given three invited presentations related to nuclear materials research.<div class="ExternalClass943D906E92974EA594628EBD350A953E"><p>​Master of Science in Physics, University of Linkoping, Sweden, 2006</p></div><div class="ExternalClassDE95C792D50741A49ED718790E387B5A"><p>​Light Water Reactor Fuel Expert role and group lead for the Focused Ion Beam (FIB) group. Principal investigator for development and post irradiation research and development projects. Research activities that use FIBs and the development of novel techniques for characterizing materials.</p></div><div class="ExternalClassF200267B700940D2A7BF72FE70324C49"><p>​Member of the American Nuclear Society<br> Ad-hoc journal reviewer<br> Grant proposal reviewer</p></div><div class="ExternalClassD4C0F13EE22E4735A348E9FAF3A2A5E3"><ol><li><p>T. Seymour, P. Frankel, L. Balogh, T. Ungár, S.P. Thompson, D. Jädernäs, J. Romero, L. Hallstadius, M.R. Daymond, G. Ribárik, M. Preuss. "Evolution of dislocation structure in neutron irradiated Zircaloy-2 studied by synchrotron x-ray line profile analysis", Acta Materialia, Volume 126, 2017.</p></li><li><p>Harte, D. Jädernäs, M. Topping, P. Frankel, C.P. Race, J. Romero, L. Hallstadius, E.C. Darby, M. Preuss, "The effect of matrix chemistry on dislocation evolution in an irradiated Zr alloy", Acta Materialia, Volume 130, 2017.</p></li><li><p>Harte, M. Topping, P. Frankel, D. Jädernäs, J. Romero, L. Hallstadius, E.C. Darby, M. Preuss, "Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy", Journal of Nuclear Materials, Volume 487, 2017.</p></li><li><p>J. Chen, D. Jädernäs, F. Lindberg, M. Bjurman, K. Kese, A. Jenssen, M. Cocco, H. Johansson, "Microstructures of oxide films formed in Alloy 182 BWR core shroud support leg cracks", Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors</p></li><li><p>Jenssen, J. Chen, F. Lindberg, D. Jadernas, P. Ekstrom, P. Efsing. "Effect of Neutron Irradiation on the Oxides formed on Type 316 Stainless Steel", Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors</p></li><li><p>M. Bjurman, D. Jädernäs, K. Kese, A. Jenssen, J. Chen, M. Cocco, H. Johansson. "Root cause analysis of cracking in Alloy 182 BWR core shroud support leg cracks", Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors</p></li><li><p>D. Jädernäs, F. Corleoni, P. Tejland, A. Puranen, J. Matsunaga, "Chemical and Structural Characterization of Ramp Tested Fuel with Different Additives", OECD/NEA/WGFS Workshop on Pellet Cladding Interaction</p></li><li><p>M. Topping, A. Harte, P. Frankel, C. Race, G. Sundell, M. Thuvander, H.-O. Andrén, D. Jadernas, P. Teiland, J. Romero, E. C. Darby, S. Dumbill, L. Hallstadius, M. Preuss. "The Effect of Iron on Dislocation Evolution in Model and Commercial Zirconium Alloys", 18th International Symposium on Zirconium in the Nuclear Industry, 2016</p></li><li><p>J. Karlsson, G. Grandi, C. Struzik, I. Porter, D. Schrire, E. Dalborg, A. Moeckel, D. Jädernäs, P. Magnusson, F. Corleoni, A. Puranen, "Fuel Performance Modeling of the Halden-Studsvik Counter-Part Test Rod", The Extended Halden Program Group Meeting 2016</p></li><li><p>P. Magnusson, C. Adamsson, D. Jädernäs, G. Rönnberg, D. Schrire, A. Alvestav, M. Seidl. "A study of transient FGR by integral LOCA tests", Light Water Reactor (LWR) Fuel Performance Meeting/Top Fuel 2016</p></li><li><p>J. Chen, D. Jadernas, M. Bjurman, F. Lindberg, K. Kese, A. Jenssen, H. Johansson, M. Cocco, "TEM Examination of Oxide Films Formed in the Crack Opening of Alloy 182 Weld Metal under BWR Normal Water Chemistry Conditions", Proceedings of the 20th Nuclear Plant Chemistry Conference, NPC 2016</p></li><li><p>EBSD in nuclear applications</p></li><li><p>D. Jädernäs, INVITED SPEAKER - 14th European Workshop on Modern Developments and Applications in Microbeam Analysis 2015.</p></li><li><p>O. Roth, A. Puranen, M. Granfors, D. Cui, C. Askeljung, D. Jädernäs, Overview of spent nuclear fuel properties affecting the release of radionuclides under long-term storage conditions, Miller Conference on Radiation Chemistry 2015</p></li><li><p>D. Jädernäs, P. Tejland, A. Puranen, M. Granfors, J. Matsunaga, PCI mitigation using fuel additives, Light Water Reactor (LWR) Fuel Performance Meeting/Top Fuel 2015.</p></li><li><p>Curti, A. Puranen, D. Grolimund, D. Jädernas, D. Sheptyakova, A. Mesbah, Characterization of selenium in UO2 spent nuclear fuel by micro X-ray absorption spectroscopy and its thermodynamic stability</p></li><li><p>Environmental Science: Processes & Impacts, 2015, 17, 1760-1768</p></li><li><p>Harte, T. Seymour, E.M. Francis, P. Frankel, S.P. Thompson, D. Jädernäs, J. Romero, L. Hallstadius and M. Preuss, Advances in Synchrotron X-Ray Diffraction and Transmission Electron Microscopy Techniques for the Investigation of Microstructure Evolution in Proton- and Neutron-Irradiated Zirconium Alloys</p></li><li><p>Journal of Materials Research - Volume 30, Issue 9 (Focus Issue: Characterization and Modeling of Radiation Damage on Materials: State of the Art, Challenges, and Protocols) May 2015, pp. 1349-1365.</p></li><li><p>D. Jädernäs, P. Tejland, Electron Backscatter Diffraction of Nuclear Materials - INVITED SPEAKER - Microscopy & Microanalysis 2014, Microsc. Microanal. 20 (Suppl 3), 2014.</p></li><li><p>Iron redistribution in a zirconium alloy after neutron and proton irradiation studied by energy-dispersive E.M. Francis, A. Harte, P. Frankel, S.J. Haigh, D. Jädernäs, J. Romero, L. Hallstadius, M. Preuss, X-ray spectroscopy (EDX) using an aberration corrected (scanning) transmission electron microscope (Corrigendum in Volume 467, Part 1, December 2015, Pages 395–396). Journal of Nuclear Materials, Volume 454, Issues 1–3, November 2014, pp. 387–397.</p></li><li><p>E. Curti, A. Froideval, M. Martin, A. Bullemar, I. Gunther-Leopold, D. Jädernäs, A. Puranen, O. Roth, D. Grolimund, C.N. Borca, A. Valea, X-Ray Absorption Spectroscopy of Selenium in Unirradiated UO2 and High-Burnup UO2 Spent Fuel From the Leibstadt and Oskarshamn-3 Reactors, Final Workshop Proceedings of the Collaborative Project "Fast / Instant Release of Safety Relevant Radionuclides from Spent Nuclear Fuel".</p></li><li><p>P. Magnusson, A. Puranen, D. LeBouch, D. Jädernäs, G. Lysell, An experimental and finite element modeling study of cladding strain and localized stresses under simulated iodine-induced stress corrosion cracking PCI, LWR Fuel Performance Meeting/TopFuel 2014. </p></li><li><p>D. Jädernäs, F. Corleoni, A. Puranen, M. Gransfors, G. Lysell, P. Tejland, D. Lutz, L. Hallstadius, Microstructural and Chemical Characterization of Ramp Tested Additive Fuels, LWR Fuel Performance Meeting/TopFuel 2013. </p></li><li><p>Puranen, M. Granfors, P. Askeljung, D. Jädernäs, M. Flanagan, Burnup Effects on Fine Fuel G. Pan, A. Garde, R. Källström, A. Atwood, D. Jädernäs. Fragmentation in Simulated LOCA Testing, LWR Fuel Performance Meeting/TopFuel 2013.</p></li><li><p>High Burnup OPTIMIZED ZIRLO(TM) Cladding Performance, LWR Fuel Performance Meeting/TopFuel 2013.</p></li><li><p>J. Romero, M. Dahlbäck, M. Ivermark, L. Hallstadius, D. Jadernas, G. Ledergerber, Understanding the drivers of in-reactor growth of beta-quenched Zircaloy 2 BWR channels, 17th International Symposium on Zirconium in the Nuclear Industry 2013.</p></li></ol></div>Advanced Characterization;Nuclear;Materials Characterization;Materials Properties and Performance scientist
Jan-Fong Jue Jue<div class="ExternalClass9A2C57C3BEB4492996074AB80EA27AC7"><p>​B.S. Materials Science and Engineering, National Tsing-Hua University</p><p>Ph.D. Materials Science and Engineering, University of Utah</p></div><div class="ExternalClass2685ED3503874DFE8FF72990B0596FA5"><p>​Nuclear materials characterization using electron microscopy</p><p>Developing metallic nuclear fuels and high temperature ceramic actinide sensors</p></div><div class="ExternalClassBBA67B3A7934482FBDBA3DF85FFF7FCC"><p>​American Ceramic Society<br> Electrochemical Society<br> ASM International<br> American Nuclear Society<br> Phi Kappa Phi Honor Society </p></div><div class="ExternalClass8375553269964CA887619EF9657B13A1"><p>​More than 50 peer-reviewed publications on energy materials</p></div>Materials Science and Engineering;Nuclear Staff Scientist
Brandon Miller Miller<div class="ExternalClass965BAA6DCAEC44A89D87B2F42651ECC1"><p>​Ph.D Nuclear Engineering and Engineering Physics, University of Wisconsin-Madison, 2010</p></div><div class="ExternalClassC451AAE220954CD6BD3D346D6CBE209F"><p>​Microstructural characterization of irradiated materials focusing on nuclear fuels</p></div><div class="ExternalClass240D745E105B4C42BF449CDDD71193C6"><p>Transmission Electron Microscopy Characterization of Irradiated U-7Mo/Al-2Si Dispersion Fuel</p><p>Vol. 396, Iss. 2-3, Jan 2010, pg 234-239</p><p>J. Gan, D. D. Keiser Jr., D. M. Wachs, A. B. Robinson, B. D. Miller, T. R. Allen</p><p> </p><p>Advantages and Disadvantages of using a Focused Ion Beam to Prepare TEM samples from Irradiated U-10Mo Monolithic Nuclear Fuel</p><p>Vol. 424, Issue 1-3, May 2012, pg 38-42</p><p>B. D. Miller, J. Gan, J. Madden, JF. Jue, A. Robinson, D. D. Keiser Jr.</p></div>Nuclear Engineering scientist
Daniel Murray Murray<div class="ExternalClass3ED97ADAE4374A3E9085F9D948E16479"><p>​<span style="line-height:115%;font-family:"calibri",sans-serif;font-size:11pt;"><font color="#000000">Ph.D., Materials Chemistry, University of Nevada Reno, 2016</font></span></p></div><div class="ExternalClassCBA8EB0F3A1D41F095416F999DB4BDE8"><p>​Micro structural characterization of nuclear materials </p><p><em>In-situ</em> measurement of electronic and thermal properties of materials in the FIB</p><p>Nanostructured materials </p></div>Advanced Characterization;Materials Properties and Performance;Materials Science and Engineering;Nuclear scientist
Jian Gan, Ph.D. Gan, Ph.D. Dr. Jian Gan is the directorate fellow and department manager of the Advanced Characterization at the Idaho National Laboratory’s Materials and Fuels Complex. He has been dedicated to conducting radiation effects research leading to the development of radiation tolerant materials for 25 years. He has extensive experience using multiple techniques such as light ions, heavy ions, in-situ ion irradiation/microscopy, and neutron irradiation to conduct research focused on the relationships between radiation damage, material microstructure, and material performance on a broad range of reactor structural materials and nuclear fuels. In addition to this effective multidisciplinary approach, Dr. Gan is a recognized international expert in the nanoscale characterization of irradiated fuels and materials using transmission electron microscopy (TEM). Before joining Argonne National Laboratory-West in 2002, he did his post-doc fellowship at Pacific Northwest National Laboratory in 1999-2001. He was an assistant professor (1982-1987) and a lecturer (1987-1990) in Physics Department of Fudan University. He has been working as principle researcher and work package manager for many DOE projects and he is the member of OECD-NEA Expert Group on Innovative Structural Materials. <div class="ExternalClass5C0C0738A86040C88F66DDB9AEEAE5B2"><p>​Ph.D. in Nuclear Engineering, University of Michigan-Ann Arbor, September 1999.<br> M.S. in Nuclear Engineering, University of Michigan-Ann Arbor, August 1994.<br> M.S. in Physics, Central Michigan University, August 1992.<br> B.S. in Physics, Fudan University, China, July 1982.<br><br><br></p></div><div class="ExternalClass2906A56DFB6542B6BA25B3D61C76E0A8"><p>(partial list of over 110 peer-reviewed publications)<br></p><ol><li>Jian Gan; Dennis D. Keiser; Brandon D. Miller; Jan-Fong Jue; Adam B. Robinson; James W. Madden; "TEM Characterization of the Irradiated U-7Mo/Mg Dispersion Fuel" J. Nucl. Mater. 494 (2017) 380-397.</li><li>J. Gan; B.D. Miller; D.D. Keiser Jr.; J.F Jue; J.W. Madden; A.B. Robinson; H. Ozaltun; G. Moore; M.K. Meyer "Irradiated Microstructure of U-10Mo Monolithic Fuel Plate at Very High Fission Density" J. Nucl. Mater. 492 (2017) 195-203.</li><li>J. Gan, D.D. Keiser, Jr., B.D. Miller, N. Eriksson, Y.H. Sohn, M. Kirk, "Irradiation Induced Structural Change in Mo<sub>2</sub>Zr Intermetallic Phase", Scripta Materialia 121 (2016) 56-60.</li><li>J. Gan, D.D. Keiser, Jr.; B.D. Miller; A.B. Robinson, D.M. Wachs, and Mitch Meyer, "Thermal Stability of Fission Gas Bubble Superlattice in Irradiated U-10Mo Fuel", J. Nucl. Mater. 464 (2015) 1-5.</li><li>J. Gan, B. D. Miller, D. D. Keiser, Jr., A. B. Robinson, J. W. Madden, P. G. Medvedev, D. M. Wachs, "Microstructural Characterization of Irradiated U-7Mo/Al-5Si Dispersion Fuel to High Fission Density", J. Nucl. Mater. 454 (2014) 434-445.</li><li>J. Gan, D.D. Keiser, D. Wachs, B.D. Miller, T. Allen, M.A. Kirk, J. Rest, "Microstructure of RERTR DU-Alloys Irradiated with Kr Ions up to 100 dpa", J. Nucl. Mater. 411 (2011) 174-180.</li><li>J. Gan, D. D. Keiser, Jr., B. D. Miller, J.F. Jue, A. B. Robinson, P. Medeved and D. M. Wachs, "Microstructure of Irradiated U<sub>3</sub>Si<sub>2</sub>/Al Silicide Dispersion Fuel", J. Nucl. Mater. 419 (2011) 97-104.</li><li>J. Gan, D.D. Keiser, B.D. Miller, M.A. Kirk, J. Rest, T.R. Allen and D.M. Wachs, "Kr Ion Irradiation Study of the Depleted-Uranium Alloys", J. Nucl. Mater. 407 (2010) 48-54.</li><li>J. Gan, Y. Yang, C.A. Dickson, T.R. Allen, "Proton Irradiation Study of GFR Candidate Ceramics", J. Nucl. Mater. 389 (2009) 317-325.</li><li>J. Gan, G. S. Was and R. E. Stoller,"Modeling of Microstructure Evolution in Austenitic Stainless Steels Irradiated under Light Water Reactor Condition", J. Nucl. Mater. 299 (2001) 53.<br></li></ol><p><br></p></div> Fellow, Department Manager of Advanced Characterization, Materials and Fuels Complex