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Jan-Fong Juehttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=448Jan-Fong 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;Nuclearhttps://bios.inl.gov/BioPhotos/Jan-FongJue.JPGDistinguished Staff Scientist
Brandon Millerhttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=450Brandon 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 Engineeringhttps://bios.inl.gov/BioPhotos/BrandonMiller.JPGResearch scientist
Daniel Murrayhttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=451Daniel 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;Nuclearhttps://bios.inl.gov/BioPhotos/Danielmurray.JPGInstrument scientist
Lingfeng Hehttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=452Lingfeng HeLingfeng He is a senior R&D scientist and instrument scientist at Idaho National Laboratory. Dr. He received his PhD degree in materials science at Chinese Academy of Sciences in China in 2009, and then worked as postdoctoral research associate and assistant scientist at Nagaoka University of Technology, Japan, and the University of Wisconsin-Madison before joined INL in 2014. Dr. He is interested in materials behavior under extreme environments, with a focus on environmental degradation of materials in nuclear power systems. Dr. He’s goal is to understand how the processing and radiation/corrosion environments change the microstructure of materials and its effects on the mechanical and thermal properties of materials. He probed these interactions by virtue of cutting-edge electron microscopy and spatially resolved spectroscopy techniques. His current research projects include microstructure characterization of as-fabricated and irradiated nuclear fuels (oxide fuels, nitride fuels, silicide fuels, and metallic fuels) as well as advanced structural materials (ceramics, steels and nickel based alloys). He has authored/co-authored over 65 peer-reviewed journal papers and holds 5 patents.<div class="ExternalClass37EBF958B9AA436C96F5DC35BD3D71D8"><p><span aria-hidden="true"></span>B. Eng. in Metallurgical Science and Engineering, Central South University, China, 2003<span aria-hidden="true"></span></p><p>Ph.D. in Materials Science, Chinese Academy of Sciences (CAS), China, 2009</p><p> </p></div><div class="ExternalClassBCF73949B73F4CD8AFF10C5F8E841412"><p>​Materials behavior under extreme environments, with a focus on environmental degradation of materials in nuclear power systems. Understanding how the processing and radiation/corrosion environments change the microstructure of materials and their effects on the mechanical and thermal properties of materials.</p></div><div class="ExternalClassD63A6609584E44A1AF7F50AD90108533"><p>The Minerals, Metals & Materials Society, since October 2016</p><p>Grant proposal and Journal reviewer for US Department of Energy (DOE), Office of Nuclear Energy, Nuclear Energy University Program (NEUP), Nuclear Science User Facility (NSUF), DOE Office of Science, SBIR/STTR, Laboratory Directed Research and Development (LDRD) at Idaho National; 27 peer-reviewed journals</p></div><div class="ExternalClass593185FCE823417995A13416017932F6"><p>L. He, J.M. Harp, A.R. Wagner, R.E. Hoggan, and K.R. Tolman: Hydrothermal Synthesis of Silicon Oxide Clad Uranium Oxide Nanowires, J. Am. Ceram. Soc., 101 (2018) 1004-1008.</p><p><br>T. Yao, B. Gong, L. He, J. Harp, M. Tonks, J. Lian: Radiation-induced Grain Subdivision and Bubble Formation in U3Si2 at LWR Temperature, J. Nucl. Mater., 498 (2018) 169-175.</p><p><br>L. He, X.M. Bai, J. Pakarinen, B. Jaques, J. Gan, A.T. Nelson, A. El-Azab, and T.R. Allen: Bubble Evolution in Kr-irradiated UO2 during Annealing, J. Nucl. Mater., 496 (2017) 242-250.</p><p><br>S.T. Nguyen, T. Nakayama, H. Suematsu, T. Suzuki, L. He, H.-B. Cho, and K. Niihara: Strength Improvement and Purification of Yb2Si2O7-SiC Nanocomposites by Surface Oxidation Treatment, J. Am. Ceram. Soc., 100 (2017) 3122-3131.</p><p><br>L. He, J.M. Harp, R.E. Hoggan, and A.R. Wagner: Microstructure Studies of Interdiffusion Behavior of U3Si2/Zircaloy-4 at 800 and 100°C, J. Nucl. Mater., 486 (2017) 274-282.</p><p><br>D.J. Tallman, L. He, J. Gan, El'ad N. Caspi, E.N. Hoffman, and M.W. Barsoum: Effect of Neutron Irradiation of Ti3SiC2 and Ti3AlC2 in the 121-1085°C Temperature Range, J. Nucl. Mater., 484 (2017) 120-134.</p><p><br>G. Zheng, L. He, D. Carpenter, and K. Sridharan: Corrosion-induced Microstructural Developments in 316 Stainless Steel during Exposure to Molten Li2BeF4 (FLiBe) Salt, J. Nucl. Mater., 482 (2016) 147-155.<br>M. Khafizov, J. Pakarrinen, L. He, H.B. Henderson, M.V. Manuel, B. Jacques, D.P. Butt, A. El-Azab, D. Hurley: Subsurface Imaging of Grain Microstructure Using Picosecond Ultrasonics, Acta Mater., 112 (2016) 209-215. </p><p><br>D.J. Tallman, L. He, B.L. Garcia-Diaz, E.N. Hoffman, G. Kohse, R.L. Sindelar, and M.W. Barsoum: Effect of Neutron Irradiation on Defect Evolution in Ti3SiC2 and Ti2AlC, J. Nucl. Mater., 468 (2016) 194-206.</p><p><br>G. Zheng, B. Kelleher, L. He, G. Cao, M. Anderson, T. Allen, and K. Sridharan: High-Temperature Corrosion of UNS N10003 in Molten Li2BeF4 (FLiBe) Salt, Corrosion, 71 (2015) 1257-1266.</p><p><br>J. Pakarinen, L. He, A.-R. Hassan, M. Gupta, A. El-Azab, and T.R. Allen: Annealing-Induced Lattice Recovery in Room-Temperature Xenon Irradiated CeO2: X-ray Diffraction and Electron Energy Loss Spectroscopy Experiments, J. Mater. Res., 30 (2015) 1555-1562.</p><p><br>L. He, B. Valderrama, A-R. Hassan, J. Yu, M. Gupta, J. Pakarinen, H.B. Henderson, J. Gan, M.A. Kirk, A.T. Nelson, M.V. Manuel, A. El-Azab, and T.R. Allen: Bubble Formation and Kr Distribution in Kr-irradiated UO2, J. Nucl. Mater., 456 (2015) 125-132. </p><p><br>L. He, M.A. Kirk, M. Gupta, J. Pakarinen, J. Gan, A.T. Nelson, A. El-Azab, and T.R. Allen: In Situ TEM Observation of Dislocation Evolution in Polycrystalline UO2, JOM, 66 (2014) 2553-2561.</p><p><br>B. Valderrama, L. He, H.B. Henderson, J. Pakarinen, B. Jacques, J. Gan, D.P. Butt, T.R. Allen, and M.V. Manuel: Effect of Grain Boundaries on Krypton Segregation Behavior in Irradiated Uranium Dioxide, JOM, 66 (2014) 2562-2568.</p><p><br>J. Pakarinen, M. Khafizov, L. He, C. Wetteland, J. Gan, A. Nelson, D.H. Hurley, A. El-Azab, and T.R. Allen: Microstructures and Thermal Conductivity Evolution in 3.9 MeV He2+ Irradiated Depleted UO2, J. Nucl. Mater, 454 (2014) 283-289.</p><p><br>L. He, J. Pakarinen, M.A. Kirk, J. Gan, A.T. Nelson, A. El-Azab, and T.R. Allen: Microstructure Evolution in Xe-Irradiated UO2 at Room Temperature, Nucl. Instrum. Meth. B, 330 (2014) 55-60.</p><p><br>L. He, P. Roman, B. Leng, K. Sridharan, M. Anderson, and T.R. Allen: Corrosion Behavior of an Alumina Forming Austenitic Steel Exposed to Supercritical Carbon Dioxide, Corros. Sci., 82 (2014) 67-76. </p><p><br>M. Khafizov, I.-W. Park, A. Chernatynskiy, L. He, J. Lin, J.J. Moore, D. Swank, T. Lillo, S.R. Phillpot, A. El-Azab, and D. Hurley: Thermal Conductivity in Nanocrystalline Ceria Thin Films, J. Am. Ceram. Soc., 97 (2014) 562-569. </p><p><br>L. He, J. Shirahata, H. Suematsu, T. Nakayama, T. Suzuki, and K. Niihara: Synthesis of BN Nanosheet/Nanotube-Fe Nanocomposites by Pulsed Wire Discharge and High-temperature Annealing, Mater. Lett., 117 (2014), 120-123.</p><p><br>J. Pakarinen, L. He, M. Gupta, A. Nelson, A. El-Azab, and T.R. Allen: 2.6 MeV Proton Irradiation Effects on the Surface Integrity of Depleted UO2, Nucl. Instrum. Meth. B, 319 (2014) 100-106.</p><p><br>L. He, M. Gupta, C.A. Yablinsky, J. Gan, M.A. Kirk, X.M. Bai, J. Pakarinen, and T.R. Allen: In Situ TEM Observation of Dislocation Evolution in Kr-Irradiated UO2 Single Crystal, J. Nucl. Mater., 443 (2013) 71-77.</p><p><br>L. He, C.A. Yablinsky, M. Gupta, J. Gan, M.A. Kirk, and T.R. Allen: Transmission Electron Microscopy Investigation of Krypton Bubbles in Polycrystalline CeO2, Nucl. Tech., 182 (2013) 164-169.</p><p><br>Y. Zhou, L. He, Z. Lin, and J. Wang: Synthesis and Structure-Property Relationships of a New Family of Layered Carbides in Zr-Al(Si)-C and Hf-Al(Si)-C Systems, J. Eur. Ceram. Soc., 33 (2013) 2831-2865.</p></div>Advanced Characterization;Materials Science and Engineering;Materials Properties and Performancehttps://bios.inl.gov/BioPhotos/lingfenghe.JPG<div class="ExternalClass109E545AFA5C473EABF1007D7CE7DBD0"><p><a href="http://orcid.org/0000-0003-2763-1462">ORCID</a></p></div>Senior staff scientist and instrument scientist
Mukesh Bachhavhttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=453Mukesh 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 Performancehttps://bios.inl.gov/BioPhotos/mukeshbachhav.JPGInstrument scientist
Fidelma Di Lemmahttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=454Fidelma 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 https://www.researchgate.net/profile/Fidelma_Di_Lemma/contributions</p></div>Advanced Characterization;Nuclear Engineeringhttps://bios.inl.gov/BioPhotos/fidelmadilemma.JPGInstrument Scientist/Metallography Scientist
Mitchell K. Meyer, Ph.D.https://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=306Mitchell K. Meyer, Ph.D.Dr. Mitchell K. Meyer is the director of the Characterization and Advanced PIE division at the Idaho National Laboratory’s Materials and Fuels Complex. In this position since February 2015, he has been responsible for strategic planning of new nuclear fuels and material research program, as well as the construction and outfitting of two major new facilities. He studied ceramic engineering at Iowa State University, where he earned his bachelor’s, master’s and doctoral degrees. He came to Idaho in 1996 as a staff ceramic engineer at Argonne National Laboratory-­West and by 2005 he was the U.S. Lead for AFCI and gas-cooled fast reactor fuels, interfacing with research partners in Great Britain, France and the European Union. While director of INL’s Nuclear Fuels and Materials Division from 2011 to 2015, he served as national technical lead for RERTR Fuel Development.<div class="ExternalClass8FAEE6BE1BBC42B785ECB3E1F02E3714"><div><p>​Bachelor’s, master’s and doctoral degrees in ceramic engineering, Iowa State University</p></div></div>Nuclear Fuelshttps://bios.inl.gov/BioPhotos/Mitch_Meyer.jpgDirector of Characterization and Advanced PIE
Jian Gan, Ph.D.https://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=737Jian 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>https://bios.inl.gov/BioPhotos/JianGan.jpgDirectorate Fellow, Department Manager of Advanced Characterization, Materials and Fuels Complex
Kevin Tolmanhttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=428Kevin Tolman<div class="ExternalClass4D2ED4A157CD44D080A7198F558CEB2A"><p>​Ph. D. in Materials Science & Engineering, Boise State University, 2016 </p><p>Focus on microstructural characterization and structure-property relationships in dielectrics, ferroelectrics, and ionic conductors</p></div><div class="ExternalClass3A74A00D87ED48FDAF43A3C9C94BC44B"><table width="100%" class="ms-rteTable-default" cellspacing="0"><tbody><tr><td class="ms-rteTable-default" style="width:50%;"><span style="font-size:9pt;">National Postdoctoral Association</span></td><td class="ms-rteTable-default" style="width:50%;text-align:left;"><span style="font-size:9pt;">2017 – 2018</span></td></tr><tr style="text-align:left;"><td class="ms-rteTable-default"><span style="font-size:9pt;">Material Science & Engineering Club Member and Officer (<em>treasurer</em>)</span></td><td class="ms-rteTable-default"><span style="font-size:9pt;">2015 – 2016</span></td></tr><tr style="text-align:left;"><td class="ms-rteTable-default"><p><span style="font-size:9pt;">American Ceramic Society & Materials Advantage</span></p><p><span style="font-size:9pt;">National Society of Leadership and Success</span></p></td><td class="ms-rteTable-default"><p><span style="font-size:9pt;">2013 – 2016 </span></p><p><span style="font-size:9pt;">2010 – 2015</span></p></td></tr><tr style="text-align:left;"><td class="ms-rteTable-default"><span style="font-size:9pt;">Golden Key International Honor Society</span></td><td class="ms-rteTable-default"><span style="font-size:9pt;">2010 – 2015</span></td></tr></tbody></table></div><div class="ExternalClassFA3F8168317B47368E4B08BC5901AD92"><ol><li>L. He, J. M. Harp, A.R. Wagner, R.E. Hoggan, K.R. Tolman, (2017) "<em>Hydrothermal synthesis of silicon oxide clad uranium oxide nanowires</em>", Journal of the American Ceramic Society. [in press]</li><li>Tolman, K.R. and Ubic, R., (2016) "<em>An empirical model for perovskite tetragonality</em>." Journal of Alloys and Compounds, 690, 825-835. </li><li>Tolman, K., Ubic, R., Liu, B., Williamson, I., Bedke, K., Nelson, E. B., … & Chen, X. M. (2016). "<em>Empirical Evidence for A</em><em>‐</em><em>Site Order in Perovskites</em>." Journal of the American Ceramic Society. </li><li>K. Tolman, R Ubic, WM Kriven, H Kungl. "<em>Structural Effect of Aliovalent Doping in Lead Perovskites</em>." Journal of Solid State Chemistry. 225 (2015): 359-367. </li><li>K. Tolman. "<em>Vacancy Modeling in Lead Titanate and Lead Zirconate Titanate</em>." Ceramic transactions 249 (2014) (1042-1122): 215. </li><li>R. Ubic, K Tolman, K Chan, N Lundy, S Letourneau, WM Kriven. "<em>Effective size of vacancies in aliovalently doped SrTiO3 perovskites</em>." Journal of Alloys and Compounds. 575 (2013): 239–245.</li></ol></div>Nuclear Fuels;Materials Science and Engineering;Thermophysical Properties of Nuclear Fuel Materials https://bios.inl.gov/BioPhotos/KevinTolman.jpgPostdoctoral Research Associate; Instrument Scientist
Cynthia Adkinshttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=431Cynthia 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>, et.al., "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>, et.al., "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>, et.al., "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 https://bios.inl.gov/BioPhotos/CynthiaAdkins.jpgLead Scientist – Thermal Properties
Daniel Jadernashttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=447Daniel JadernasDaniel 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 Performancehttps://bios.inl.gov/BioPhotos/danieljadernas.JPGResearch scientist
Karen Wrighthttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=396Karen WrightKaren 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 Fuelshttps://bios.inl.gov/BioPhotos/KarenWright.JPGInstrument Scientist