Ian Farnan is Professor of Earth and Nuclear Materials in the Department of Earth Sciences, University of Cambridge. His research is focused on the structure, durability and fabrication of nuclear materials and naturally occurring radioactive minerals and the underpinning science for the disposal of radioactive waste. He is the Consortium Lead for the CaFFE (Carbides for Future Fission Environments) UK EPSRC to examine new materials for accident tolerant fuels and led the UK NDA-EPSRC research programme on the suitability of UK AGR fuel for geological disposal. Dr Farnan is involved with the use of international facilities for radiochemical research and the development of analytical techniques at the facilities to support his research and the nuclear research community. He was coordinator of the Euratom FP7 programme EURACT-NMR and served on the Scientific Advisory Committee of the Environmental and Molecular Sciences Directorate of Pacific Northwest National Laboratory (2007-15). He is Chair of Cambridge Nuclear Energy Centre and advises the UK Nuclear Decommissioning Authority on the disposal of high activity materials. Farnan has held a Visiting Professorship at Stanford University and visiting scientist positions at the Australian Nuclear Science and Technology Organisation and at the European Commission Institute for Transuranium Elements (JRC).
Nuclear power from thorium fuel cycles is being explored around the world to extend uranium resource and to reduce the quantity of long-lived nuclear waste generated by civilian nuclear power production. Significant research and development efforts towards fuel cycles using thorium as the primary fertile material in place of uranium have occurred in India, Canada (Thorium Power), China (SINAP), Norway (ThorEnergy), the United States (Flibe, Thorcon), and elsewhere. Protactinium-233 is produced during the neutron irradiation of thorium-232 in a nuclear reactor. Protactinium-233 is a precursor to uranium-233, where uranium-233 is an accountable nuclear material under international nuclear safeguards. Currently, there are no conceptual approaches for monitoring and verifying protactinium-233 during thorium irradiation and spent fuel reprocessing. This presentation will describe a collaboration between researchers at Sandia National Laboratories and Oak Ridge National Laboratory to identify leading thorium fuel cycle candidates and to quantify protactinium production rates in those fuel cycles. Eva Uribe is an alumna of the Nuclear Science and Security Consortium, and she will also provide a brief overview of her early career since graduating from UC Berkeley.
Dr. Eva C. Uribe is a senior systems research analyst at Sandia National Laboratories. As a systems analyst, she teams across disciplines to provide unbiased and objective information and frameworks for decisionmakers to understand the risks, benefits, and unintended consequences of options within complex national security landscapes. Her current portfolio includes projects in advanced nuclear fuel cycle safeguards, spent nuclear fuel reprocessing, nuclear deterrence, nuclear nonproliferation, and cyber systems analysis. Prior to joining the laboratory in 2017, she was a Stanton Nuclear Security postdoctoral fellow at the Center for International Security and Cooperation at Stanford University, where she investigated the implications of advanced spent fuel reprocessing capabilities in thorium fuel cycles on nuclear nonproliferation and the international safeguards regime. Eva graduated from the University of California, Berkeley with a Ph.D. in chemistry in 2016. She conducted her graduate research as an affiliate of the Heavy Element Nuclear and Radiochemistry Group at Lawrence Berkeley National Laboratory. Her dissertation focused on understanding the interaction between aqueous actinide and lanthanide species and organically-modified, high-surface area mesoporous silica materials, using solid-phase nuclear magnetic resonance spectroscopy. She also collaborated with the Goldman School of Public Policy to conduct policy analysis on the use of cross-domain deterrence in American foreign policy. Eva graduated from Yale University in 2011 with a B.S. in chemistry and a double major in political science. She was a Next Generation Safeguards Initiative intern in the Nonproliferation Division at Los Alamos National Laboratory in the summers of 2008 and 2009.
Metals and minerals remain at the basis of modern society and their affordable and
environmentally respectable extraction and recycling is required. A global population of 9 billion
people by 2050 and global issues such as greenhouse gas emissions provide unique opportunities
for the deployment of new technologies for metals extraction and processing. Anticipating
affordability and deployment of sustainable electric power generation , the electrification and
intensification of metals and mining industry processes is becoming a possibility. This seminar
starts with reporting a methodology and analysis of existing extraction processes (e.g., mining
and pyrometallurgy of copper sulfides, ironmaking, and aluminium electrolysis) from an
electricity and cost standpoint. In a second time, the results are used to put forth a set of metrics
for alternative technologies based on electricity [2,3,4]. Finally, results for process scale-up in
molten oxides  and sulfides [5,6] are reviewed, highlighting the recent acceleration toward
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Electrochemical Society, 162(1), 13-22, (2015)
 A. Allanore, L. Yin & D. R. Sadoway, A New Anode Material for Oxygen Evolution in Molten Oxide
Electrolysis. Nature, 497(7449), 353–356, (2013)
 S. Sokhanvaran, S.-K. Lee, G. Lambotte & A. Allanore, Electrochemistry of Molten Sulfides: Copper Extraction
from BaS-Cu2S. Journal of The Electrochemical Society, 163(3), 115–120, (2016)
 S. Sahu, B. Chmielowiec & A. Allanore, Electrolytic Extraction of Copper, Molybdenum and Rhenium from
Molten Sulfide Electrolyte, Electrochimica Acta, vol. 243, 382-389 (2017)
Dr. Kotlyar has established a sustainable research program in the field of advanced nuclear reactor design and multiphysics analysis. His Computational Reactor Engineering Laboratory (CoRE) focuses on developing the next generation production tools as well as designing advanced and low cost nuclear energy systems. In this talk he will cover the design aspects and modeling challenges associated with Nuclear Thermal Propulsion (NTP) systems. Nuclear thermal propulsion is a potential technology for future crewed missions to Mars due to its high thrust, and high specific impulse (Isp). This technology is expected to enable reduced interplanetary travel times, which could increase the crew's safety by reducing exposure to cosmic radiation and other hazards of deep space travel. BWX Technologies, Inc. (BWXT) is working with NASA to develop critical reactor fuel technologies and mature the design of a low-enriched uranium engine. Dr. Dan Kotlyar’s research group is working with BWXT to support further research in NTP technology by developing a computational multiphysics framework that will allow a better understanding of the operational limits, reliability, and associated safety margins of the engine. Many of NTP design challenges are born from satisfying both the Isp and thrust to weight ratio requirements while ensuring adequate excess reactivity for the entire engine lifetime. In order to overcome these challenges multiphysics tools are required to accurately predict the core power distribution which is impacted through various phenomena.
Dr. Dan Kotlyar is an Assistant Professor in the Nuclear and Radiological Engineering, G.W.W. School of Mechanical Engineering. He received his B.Sc. in Engineering in 2008, MSc in Nuclear Engineering in 2010, and PhD in Nuclear Engineering in 2013 from Ben-Gurion University, Israel. In 2014, he joined the University of Cambridge as a Research Associate in the Engineering Design Center. In 2014, he was elected as a Research Fellow at Jesus College. He is the recipient of the NRC Faculty Development Fellowship. Dr. Kotlyar’s research interests include development of numerical methods and algorithms for coupled Monte Carlo, fuel depletion and thermal hydraulic codes. In particular, he specializes in applying these methods to the analysis of advanced reactor systems. Dr. Kotlyar’s research also focuses on optimizing the performance of various fuel cycles in terms of fuel utilization, proliferation, and cost. Dr. Kotlyar’s group is actively engaged to support the nuclear industry with modeling and simulation challenges related to advanced concepts. Dr. Kotlyar profoundly believes in education through research and thus integrates practical reactor system design into his lectures.
José N. Reyes, Jr., P.E., Nuclear Engineering Ph.D. and M.S. Univ. of Maryland, B.S. Univ. of Florida is the Co-founder and Chief Technology Officer of NuScale Power. He is co-inventor of the NuScale small modular reactor with over 110 patents granted or pending in 20 countries. He is an expert on nuclear plant scaling, passive safety, and testing. He is Professor Emeritus and former head of the Dept. of Nuclear Engineering at Oregon State University. He is an ANS Fellow and Member of the National Academy of Engineering.
Mekhail Anwar, MD PhD
Associate Professor, Radiation Oncology
profiles.ucsf.edu/mekhail.anwar | anwarlab.ucsf.edu
We will discuss how to personalize cancer therapy through the development of new integrated circuit-based platforms for detecting both the delivery of charged particle therapy (CPT).
Real-time in vivo dosimetry - at the single particle level - holds the key to unlocking the power of personalized theranostics with both 𝛼 and β particles and the precision of proton therapy. The impact of theranostics using Lu177 - a β emitter - is already being felt across neuroendocrine and prostate cancers. Notably, 𝛼 particles deposit over 100X more energy over just 50 µm - making them a much more powerful - and potentially preciscse - therapeutic. However, this enthusiasm is tempered by the highly variable biodistribution making in vivo dosimetry essential to safe, personalized delivery. Similarly, range uncertainty is a major limiting factor in precision targeting of charged particle therapy, and would benefit from real-time in vivo dosimetry. To address these dual challenges, we have developed SENTRI - a mm2 chip capable of single CPT measurements from within tissue - and will discuss how efforts to fuse proton therapy and personalized theranostics can improve outcomes in patients with aggressive cancers.
Mekhail Anwar is a Physician-Scientist and Associate Professor in the Department of Radiation Oncology at the University of California, San Francisco (UCSF), focusing on developing microfabricated sensors and computer chip technology (‘integrated circuits’ or ICs) for cancer detection within the body. Educated at UC Berkeley in Physics, he completed his MD at UC San Francisco, and went to the Massachusetts Institute of Technology where his Ph.D. in electrical engineering focused on using ICs for biosensing. He returned to complete his residency in Radiation Oncology at UCSF and continued as faculty, where he earned the DOD Prostate Cancer Research Program Physician Award for his work in cancer imaging. He is the recipient of the NIH Trailblazer Award for developing chip-scale imagers for cancer and was recently awarded the NIH (DP2) New Innovator Award for in vivo imaging of immunotherapy response.
The global nuclear industry has for decades used sites like Stonehenge as models for designs for long-term markers to be placed over nuclear waste repositories to ensure they are not violated in distant, imagined futures. In the US, the resulting proposal would produce a pre-formed archaeological site, a ruin that would qualify for listing as a World Heritage site in the future. This talk questions the way planners thought about materials and human intentions from the perspective of an archaeological sensibility on how materials endure and decay and what people in the past expected would happen when they created the structures we recognize as monuments today.
Rosemary Joyce received the PhD from the University of Illinois-Urbana in 1985, based archaeological fieldwork in Caribbean Honduras. A curator and faculty member in anthropology at Harvard University from 1985 to 1994, she moved to the University of California, Berkeley in 1994, initiating new archaeological fieldwork in Honduras on the emergence of settled farming villages before 1500 BC. This began her explorations of the liveliness of geological materials, and the intentions of people in the past when they built features today seen as monuments. She is the author of ten books, the latest The Future of Nuclear Waste: What Art and Archaeology Can Tell Us About Securing the World’s Most Hazardous Material (2020, Oxford University Press).
Dr. Craig Levin is a Professor in the Department of Radiology with courtesy appointments in the Departments of Physics, Electrical Engineering, and Bioengineering at Stanford University. He is a founding Member of the Molecular Imaging Program at Stanford (MIPS), and faculty member of the Stanford’s Bio-X Program, Cancer Institute, Cardiovascular Institute, and Neurosciences Institute. He is director and PI of the NIH-NCI funded Stanford Molecular Imaging Scholars (SMIS) post-doctoral training program, and Co-Director of the Stanford Center for Innovation in In Vivo Imaging (SCI^3). Dr. Levin’s also directs a 25-member research laboratory whose research interests are to explore new concepts in imaging instrumentation and computational algorithms for advancing our ability to visualize and quantify molecular and cellular pathways of disease in living subjects. To support this work he has received numerous grants from NIH, DOE, DOD, NSF, industrial sponsorship from companies such as GE, Siemens, and Philips, as well as research awards from numerous non-profit foundations. Dr. Levin has over 170 peer-reviewed publications and 26 awarded patents.
Molten fluoride salts are ionic liquids that are employed in nuclear reactors as coolant or nuclear fuel solvents. 2LiF-BeF2 (FLiBe) is an ionic liquid that is of particular interest for application in nuclear reactors due to its neutronic properties. While the fluoride salts are ionic liquids, the beryllium constituent is known to form partly covalent associates with the fluorine, leading for formation of complex ions in the ionic melt. The implications of this complexation on the chemical and thermophysical properties of the salt are only partly understood. This talk will provide examples of unexpected observations in molten fluoride salts relevant to nuclear applications, including reactions of FLiBe with hydrogen.
Raluca Scarlat is an assistant professor at UC Berkeley, in the Department of Nuclear Engineering. Professor Scarlat has a Ph.D. in Nuclear Engineering from UC Berkeley and a B.S. in Chemical and Biomolecular Engineering from Cornell University. Raluca Scarlat’s research focuses on chemistry, electrochemistry and physical chemistry of high-temperature inorganic fluids and their application to energy systems. She has experience in design and safety analysis of fluoride-salt-cooled high-temperature reactors (FHRs) and Molten Salt Reactors (MSRs), and high-temperature gas cooled reactors (HTGRs). Her research includes safety analysis and design of nuclear reactors and engineering ethics.