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<h1>
Associate Professor
University of Idaho - Idaho Falls Center for Higher Education
Department of Nuclear Engineering and Industrial Management
rborrelli@uidaho.edu
@TheDoctorRAB
</h1>
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# Education
**University of California-Berkeley**
**Doctor of Philosophy, Nuclear Engineering**
*Radionuclide transport modeling with bentonite extrusion*
Examination fields: Mathematical modeling, Subsurface nuclear technology
J. Ahn (Chair), W. E. Kastenberg, T. I. Zohdi
*2006*
**Worcester Polytechnic Institute**
**Master of Science, Civil/Environmental Engineering**
*Characterization of background radiation in the environment*
J. C. O’Shaughnessy
*1999*
**Worcester Polytechnic Institute**
**Bachelor of Science, Mechanical Engineering with high distinction**
*Real time PLC-based reactivity modeling by inverse point kinetics*
Leo M. Bobek
*1996*
___
# Research experience
**University of Idaho, Idaho Falls, College of Engineering, Nuclear Engineering Program**
**Associate Professor**
*May 2021 - *
**Assistant Professor**
*July 2015 - May 2021*
Research efforts are focused on scientific computing applications to safeguardability of the advanced fuel cycle.
Coordinator - Nuclear Power Plant Decommissioning and Used Fuel Management Certificate
*August 2019 - present*
Affiliate - Boise State University Energy Policy Institute
*August 2019 - present*
State of Idaho Professional Engineer, Faculty Restricted
*October 2019 - present*
**University of California-Berkeley, Department of Nuclear Engineering**
**Postdoctorate researcher**
A safeguards methodology is developed for remotely-handled nuclear materials facilities that proposes functional design components and a risk-informed framework in an effort to integrate safeguards with safety and security into facility design.
*2009-12*
**The University of Tokyo, Department of Nuclear Engineering/Management**
**Research associate**
Mathematical models for mass transport in the engineered barrier system of a high-level nuclear waste repository are established for bentonite extrusion and radionuclide transport under different environmental conditions to assess potential impacts on performance assessment.
*2007-09*
**University of California-Berkeley, Department of Nuclear Engineering**
**Postdoctorate researcher**
Mathematical modeling of mass transport in the engineered barrier system of a high-level nuclear waste repository continued, to assess the potential of extruding bentonite to confine radionuclides.
*2007*
**University of California-Berkeley, Department of Nuclear Engineering**
**Doctoral candidate**
The dissertation thesis focused on the mathematical modeling of mass transport in the engineered barrier system of a high-level nuclear waste repository. A mass transport model was established for radionuclides in a porous medium, bentonite extrusion model in a planar fracture to assess the potential to confine radionuclides.
*2005-06*
___
# Related research experience
**Earth Sciences Division, Lawrence Berkeley National Laboratory**
**Intern**
Conducted data analysis for chaotic modeling of water flow in the unsaturated zone.
*2001-02*
**Leslie C. Wilbur Nuclear Reactor Facility, Worcester Polytechnic Institute**
**Major Qualifying Project**
The Major Qualifying Project synthesizes previous undergraduate studies to solve problems or perform tasks in the major field and communicate results effectively. For this project, a logic algorithm was developed for reactivity derived from point kinetics equations and a programmable logic controller was modified for real time collection of data during nuclear reactor operation for use with experimental coursework and maintenance procedures.
*1995-96*
___
# Related professional experience
**Leslie C. Wilbur Nuclear Reactor Facility, Worcester Polytechnic Institute**
**Assistant Radiation Safety Officer**
▪ Responded to emergencies concerning incidents involving radioactive material
▪ Maintained records of radiation exposures and dosimetry to campus personnel
▪ Maintained the full and current inventory of radioisotopes
▪ Performed calibrations for radiation detectors
▪ Instructed all radiological and nuclear reactor laboratory safety training
▪ Performed secretarial duties for Radiation, Health, and Safety Committee
*1996-99*
**Leslie C. Wilbur Nuclear Reactor Facility, Worcester Polytechnic Institute**
**Senior Nuclear Reactor Operator #70145**
▪ Operated the university nuclear reactor for experimental research projects
▪ Trained reactor operator license candidates
▪ Performed corrective and preventative maintenance of reactor systems
▪ Modified operator training program to a computer based system
*1993-99*
___
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# Awarded projects
<p>
R. A. Borrelli (PI), Jason Barnes (Senior Adviser) - University of Idaho. Experimental determination of interactions between the radiation fields of Dragonfly’s MMRTG and Titan’s environment. Idaho NASA EPSCoR Research Initiation Grant. $82,962. 2021.05.01 - 2022.04.30.
<p>
R. A. Borrelli (PI) - University of Idaho. Online educational resources for nuclear engineering courses. University of Idaho Think Open Fellowship. $1200. 2021.01.01 - 05.31.
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<p>
Athi Varuttamaseni (PI), Shinjae Yoo (co-PI) - Brookhaven National Laboratory, R. A. Borrelli (co-PI) - University of Idaho. Adaptive control and monitoring platform for autonomous operation of advanced reactors. NEUP 20-19280. $1,000,000. 2020.10.01 - 2023.09.30.
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<p>
Lee Ostrom (PI), Richard N. Christensen, R. A. Borrelli, Haiyan Zhao (co-PIs) - University of Idaho. ORED Fall 2019 EIS: Portable XFR for use in supporting material research. ORED Equipment and Infrastructure Support. $40,000. 2019.12.01 - 2020.11.30
<p>
R. A. Borrelli (PI) - University of Idaho, Mark. D. DeHart (co-PI) - Idaho National Laboratory. Application and enhancement of MAMMOTH depletion capabilities. $33,521. 2020.01.13 - 2020.12.31
<p>
Richard N. Christensen (PI), R. A. Borrelli, Michael G. McKellar, Michael Haney, David Arcilesi (co-PIs) - University of Idaho, Richard Jacobson (co-PI) Idaho State University. NuScale Simulator at the Center for Advanced Energy Studies. Department of Energy Scientific Infrastructure Support for Consolidated Innovative Nuclear Research. $285,763. 2019.10.01 - 2020.09.30
<p>
R. A. Borrelli (PI) - University of Idaho, Dennis D. Keiser, Jr., (co-PI) - Idaho National Laboratory. Graduate Research Assistantship: Connecting U-Mo Fuel Processing, Microstructure, and Irradiation Performance. $137,292. 2018.10.01-2021.09.30
<p>
R. A. Borrelli (PI), Richard N. Christensen (co-PI) - University of Idaho, Brian T. Jaques (co-PI) - Boise State University, Piyush Sabharwall (co-PI) - Idaho National Laboratory, Mark Delligatti (co-PI) - Table Rock, LLC, Sakae Casting USA, LLC (co-PI). Modeling and design of borated aluminium cask for used fuel cooling. Idaho Global Entrepreneurial Mission (IGEM) - Idaho Commerce, $237,898. 2018.01.01-2019.05.31
<p>
R. A. Borrelli (PI) - University of Idaho, Dennis D. Keiser, Jr., (co-PI) - Idaho National Laboratory. Graduate Research Assistantship: Connecting U-Mo Fuel Processing, Microstructure, and Irradiation Performance. $36,180. 2017.11.01-2018.05.31
<p>
R. A. Borrelli (PI), Lee Ostrom (Senior Advisor) - University of Idaho, Stephen G. Johnson (Senior Advisor) - Idaho National Laboratory. Performance assessment of americium as fuel in radioisotope thermoelectric generators for deep space exploration. Idaho NASA EPSCoR Research Initiation Grant. $55,000. 2017.08.01-2018.04.30
<p>
Kelley Verner (PI), R. A. Borrelli, Marc T. Skinner, Emma Redfoot, Jieun Lee, Seth Dustin, John Peterson (co-PIs) - University of Idaho. Increasing the Go-on Rate in Southeast Idaho Through the Nexus of Food, Energy, and Water. University of Idaho Vandals Big Ideas Project. $23,984. 2017.07.01-2018.06.30
<p>
R. A. Borrelli (PI) - University of Idaho, Jason Hales (co-PI) - Idaho National Laboratory. Graduate Research Assistantship: Idaho National Laboratory Code Documentation. $35,435. 2016.10.01-2017.06.30
<p>
Vivek Utgikar (PI), Fatih Aydogan, Krishnan Raja, Raghunath Kanakala, R. A. Borrelli, Haiyan Zhao, Matthew Swenson (co-PIs) - University of Idaho. University of Idaho Nuclear Engineering Faculty Development Program. United States Regulatory Commission Faculty Development Grant. $434,048. 2015.09.29 - 2019.09.30
___
# Equipment acquisitions
<p>
University of Idaho, Idaho State University, Idaho National Laboratory. Western Services Corporation Pressurized Water Nuclear Reactor Simulator.
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# Thesis committees
## Major professor
### Current
Kelley Verner, Ph.D. Candidate - Materials science and nuclear fuels analysis
Joseph Christensen, Ph.D. - Criticality safety modeling
Teyen Widdicombe, Ph.D. - RTG satellite design
Olin Calvin, Ph.D. - Enhancement of MAMMOTH depletion capabilities
### Graduates
J. Seth Dustin, MS - High level examination of Am-241 as an alternative Fuel Source in radioisotope thermoelectric generators
John Peterson, MS - Molten salt reactor neutronics design
Emma Redfoot, MS - Allocating heat and electricity in a nuclear renewable hybrid energy system coupled with a water purification system
Jieun Lee, MS - Risk-informed safeguards of pyroprocessing for advanced nuclear fuel concepts
Trevor MacLean, MEng - Cybersecurity modeling of non-critical nuclear power plant instrumentation
Malachi Tolman, MEng - INL BISON code documentation
## Member
### Graduates
_University of Idaho_
Jacob Benjamin, Ph.D - Bounding cyber in design basis threat
John Tacke, MS - Design of an automatic voltage regulator with limited plant information
D. Devin Imholte, MS - Conceptual design of the Advanced Test Reactor non-destructive examination system
John Biersdorf, MEng - Precipitation changes to Idaho National Laboratory over time
John Bell, MS - Hierarchical inference and spoofing alarm in HVDC control systems
Winfred Sowah, MS - Thermal behavior of cold plated storage cask for used light water reactor nuclear fuels
<<<<<<< HEAD
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Trevin Lasley, MS - Criticality safety on the molten salt nuclear battery
>>>>>>> gh-pages
_Idaho State University_
Pedro Mena, MS - Reactor transient classification using machine learning
### Current
_University of Idaho_
John Carter, Ph.D. - Core design of molten salt nuclear battery
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___
# Refereed journal publications
<p>
30. Pedro Mena, R. A. Borrelli, Leslie Kerby, Survey of markets for nuclear power in western North America, Progress in Nuclear Energy [*under review*] (2021).
<p>
29. J. Seth Dustin, R. A. Borrelli. Modeling of Am-241 as an alternative fuel source in a radioisotope thermoelectric generator. Nuclear Engineering and Design, [*in press*] (2021).
<p>
28. J. Seth Dustin, R. A. Borrelli. Assessment of alternative radionuclides for use in a radioisotope thermoelectric generator. Nuclear Engineering and Design, [*in press*] (2021).
<p>
27. Jonathan Tacke, R. A. Borrelli, Dakota Roberson, Advanced frequency-domain compensator design for subsystems within a nuclear generating station, Progress in Nuclear Energy (2021) 10.1016/j.pnucene.2021.103914.
<p>
26. Pedro Mena, R. A. Borrelli, Leslie Kerby, Nuclear reactor transient diagnostics using classification and AutoML, Nuclear Technology (2021) 10.1080/00295450.2021.1905470.
<p>
25. Teyen Widdicombe, R. A. Borrelli, MCNP modelling of radiation effects of the Dragonfly mission’s RTG on Titan II: Atmospheric ionization effects, Acta Astronautica 186, 517 (2021).
<p>
24. Emma K. Redfoot, Kelley M. Verner, R. A. Borrelli, Applying analytic hierarchy process to industrial process design in a nuclear renewable hybrid energy system, Nuclear Engineering and Design (2021) [*under review*].
<p>
23. R. A. Borrelli, M. S. Delligatti, B. J. Heidrich, Borated Aluminum cask design for onsite intermediate storage - Preliminary neutronics design and certification analysis, Nuclear Engineering and Design 363, (2020) doi:10.1016/j.nucengdes.2020.110666.
<p>
22. John P. Carter, R. A. Borrelli, Neutron physics study of an integral molten salt reactor using Monte Carlo N-Particle code, Nuclear Engineering and Design 365, (2020) 10.1016/j.nucengdes.2020.110718.
<p>
21. Joseph Christensen, R. A. Borrelli, Nuclear criticality safety aspects for the future of HALEU: Evaluating heterogeneity in intermediate-enrichment uranium using critical benchmark experiments, Nuclear Science and Engineering (2020) 10.1080/00295639.2020.1819143.
<p>
20. John P. Carter, R. A. Borrelli, Integral molten salt reactor temperature sensitivities using Serpent target motion sampling, Nuclear Engineering and Design 369 (2020) 10.1016/j.nucengdes.2020.110863.
<p>
19. Teyen Widdicombe, R. A. Borrelli, MCNP modelling of radiation effects of the Dragonfly missions RTG on Titan, Acta Astronautica (2020) 10.1016/j.actaastro.2020.12.033.
<p>
18. Kaelee A. Novich, Samuel V. Pedersen, R. A. Borrelli, Richard N. Christensen, Brian J. Jaques, Synthesis of boron carbide reinforced aluminum castings through mechanical stir casting, Journal of Composite Materials (2020) 10.1177/0021998320987597.
<p>
<<<<<<< HEAD
16. Kaelee A. Novich, Samuel V. Pedersen, R. A. Borrelli, Richard N. Christensen, Brian J. Jaques, Synthesis of boron carbide reinforced aluminum castings through mechanical stir casting, Journal of Composite Materials (2020) doi.org/10.1177/0021998320987597.
=======
17. Joseph Christensen, R. A. Borrelli, Modeling heterogeneity in low-enriched uranium systems using evaluated critical benchmark experiments, Nuclear Science and Engineering (2020) [*under review*].
<p>
16. Joseph Christensen, R. A. Borrelli, Parametric study of minimum critical volume for high-assay low-enriched uranium (20%) in spherical geometry against particle size, Nuclear Science and Engineering (2020) 10.1080/00295639.2021.1940066.
>>>>>>> gh-pages
<p>
15. J. Peterson, M. Haney, R. A. Borrelli, [An overview of methodologies for cyber security vulnerability assessments conducted in nuclear power plants](https://www.sciencedirect.com/science/article/pii/S0029549319300330), Nuclear Engineering and Design 346, 75 (2019).
<p>
14. J. Lee, R. A. Borrelli, [Sensitivity analysis and application of advanced nuclear accounting methodologies on the high reliability safeguards model: Use of discrete event simulation for material throughput in fuel fabrication](https://www.sciencedirect.com/science/article/pii/S0029549318308549), Nuclear Engineering and Design 345, 183 (2019).
<p>
13. J. Lee, A. Shigrekar, R. A. Borrelli, [Hazard and operability analysis of a pyroprocessing facility](https://www.sciencedirect.com/science/article/pii/S002954931830462X), Nuclear Engineering and Design 348, 131 (2019).
<p>
12. E. Redfoot, R. A. Borrelli, [Analysis of possibilities for using a nuclear fuel cycle simulator to model a nuclear hybrid energy system](https://doi.org/10.1080/00295450.2018.1478590), Nuclear Technology 204, 249 (2018).
<p>
11. J. Lee, M. Tolman, R. A. Borrelli, [High reliability safeguards approach to remotely handled nuclear processing facilities: Use of discrete event simulation for material throughput for fuel fabrication](http://www.sciencedirect.com/science/article/pii/S0029549317303862), Nuclear Engineering and Design 324, 54 (2017).
<p>
10. R. A. Borrelli, J. Ahn, Y. Hwang, [Approaches to a practical systems assessment for safeguardability of the advanced nuclear fuel cycle](http://dx.doi.org/10.1080/00295450.2016.1273713), Nuclear Technology, 197, 248 (2017).
<p>
9. R. A. Borrelli, [Functional components for a design strategy: Hot cell shielding in the High Reliability Safeguards methodology](http://dx.doi.org/10.1016/j.nucengdes.2016.05.010), Nuclear Engineering and Design, 305, 18 (2016).
<p>
8. R. A. Borrelli, [Use of curium neutron flux from head-end pyroprocessing subsystems for the high reliability safeguards methodology](http://dx.doi.org/10.1016/j.nucengdes.2014.06.028), Nuclear Engineering and Design, 277, 166 (2014).
<p>
7. R. A. Borrelli, [A high reliability safeguards approach for safeguardability of remotely-handled nuclear facilities: 1. Functional components to system design](http://www.jnmm-digital.com/jnmm/spring_2014#pg6), Journal of Nuclear Materials Management, XLII(3), 4 (2014).
<p>
6. R. A. Borrelli, [A high reliability safeguards approach for safeguardability of remotely-handled nuclear facilities: 2. A risk-informed approach for safeguards](http://www.jnmm-digital.com/jnmm/spring_2014#pg29), Journal of Nuclear Materials Management, XLII(3), 27 (2014).
<p>
5. R. A. Borrelli, [Use of curium spontaneous fission neutrons for safeguardability of remotely-handled nuclear facilities: Fuel fabrication in pyroprocessing](http://dx.doi.org/10.1016/j.nucengdes.2013.03.025), Nuclear Engineering and Design, 260, 64 (2013).
<p>
4. R. A. Borrelli, Olivier Thivent, Joonhong Ahn, [Parametric studies on confinement of radionuclides in the excavated damaged zone due to bentonite type and temperature change](http://dx.doi.org/10.1016/j.pce.2013.05.013), Physics and Chemistry of the Earth, 65, 32 (2013).
<p>
3. R. A. Borrelli, Olivier Thivent, Joonhong Ahn, [Impacts of elevated temperatures on bentonite extrusion and radionuclide transport in the excavated damaged zone](http://www.ans.org/store/j_11683), Nuclear Technology, 174, 94 (2011)
<p>
2. R. A. Borrelli, Joonhong Ahn, [Radionuclide transport in a water-saturated planar fracture with bentonite extrusion](http://www.ans.org/pubs/journals/nt/a_4037), Nuclear Technology, 164, 442 (2008).
<p>
1. R. A. Borrelli, Joonhong Ahn, [Numerical modeling of bentonite extrusion and radionuclide migration in a saturated planar fracture](http://dx.doi.org/10.1016/j.pce.2008.10.044), Physics and Chemistry of the Earth, 33, S131 (2008).
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# Book contribution
T. MacLean, M. Haney, R. A. Borrelli, Cybersecurity modeling of non-critical nuclear power plant digital instrumentation. Critical Infrastructure Protection XIII, J. Staggs, S. Shenoi, eds. in: Chapter 5, 277.
R. A. Borrelli, [Reflections on Developing an Identity for the Third Generation Nuclear Engineer in the Post-Fukushima Society](http://www.springer.com/us/book/9783319120898), Reflections on the Fukushima Daiichi Nuclear Accident: Toward Social-Scientific Literacy and Engineering Resilience, 978-3-319-12090-4 (2015).
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# Refereed conference proceedings
<p>
30. Michael Haney, Jacob Benjamin, R. A. Borrelli, Cyberweapon nonproliferation controls for the virtual battlefield - Applying the nuclear nonproliferation regime to an unseen enemy, Proc., American Nuclear Society Winter Meeting, 30 November - 03 December 2021, Washington, D. C.
<p>
29. J. Richards, R. A. Borrelli, Development of a tool for evaluating nuclear integrated energy systems profitability for existing reactors, Proc., Proc., American Nuclear Society Virtual Winter Meeting, 16-19 November, 2020. [*virtual*]
<p>
28. J. Peterson, M. Haney, R. A. Borrelli, An overview of methodologies for cybersecurity vulnerability assessments conducted at nuclear power plants, Proc., American Nuclear Society Winter Meeting, 17-21 November, 2019, Washington, D. C.
<p>
27. C. Kolias, R. A. Borrelli, D. Barbara, A. Stavrou, Malware detection in critical infrastructures by using the electromagnetic emissions of PLCs, Proc., American Nuclear Society Winter Meeting, 17-21 November, 2019, Washington, D. C.
<p>
26. J. Christensen, R. A. Borrelli, C. S. Henkel, B. Matthews, Minimum accident of concern for uranyl sulfate solutions, Proc., American Nuclear Society Annual Meeting, 09-13 June, 2019, Minneapolis, Minnesota.
<p>
25. R. A. Borrelli, Updates on borated aluminum cask design for onsite used fuel storage, Proc., American Nuclear Society Annual Meeting, 09-13 June, 2019, Minneapolis, Minnesota.
<p>
24. T. MacLean, M. Haney, R. A. Borrelli, Cybersecurity modeling of non-critical nuclear power plant instrumentation, Proc., Thirteenth Annual IFIP WG 11.10 International Conference on Critical Infrastructure Protection, 11-13 March, 2019, Arlington, Virginia.
<p>
23. J. Lee, R. A. Borrelli, Upgrades on high reliability safeguards model for material throughput in fuel fabrication, Proc., American Nuclear Society Annual Meeting, 17-21 June, 2018, Philadelphia, Pennsylvania.
<p>
22. R. A. Borrelli, J. S. Dustin, S. Pedersen, B. J. Jaques, Design of a borated aluminum cask design for onsite used fuel storage, Proc., American Nuclear Society Annual Meeting, 17-21 June, 2018 Philadelphia, Pennsylvania.
<p>
21. R. A. Borrelli, M. S. Delligatti, Regulatory licensing pathway for a borated aluminum cask design for onsite used fuel storage, Proc., American Nuclear Society Annual Meeting, 17-21 June, 2018, Philadelphia, Pennsylvania.
<p>
20. J. S. Dustin, R. A. Borrelli, Preliminary Performance Assessment of Americium-241 as Fuel in Radioisotope Thermoelectric Generators for Deep Space Exploration, Proc., ANS NETS 2018 - Nuclear and Emerging Technologies for Space, 26 February - 01 March, 2018, Las Vegas, Nevada.
<p>
19. J. Lee, R. A. Borrelli, Hazard and operability analysis of a pyroprocessing facility, Proc., 2017 American Nuclear Society Winter Meeting, 29 October-02 November, 2017, Washington, D. C.
<p>
18. E. Redfoot, K. Verner, R. A. Borrelli, Applying preliminary hazard analysis and analytic hierarchy process to a nuclear renewable hybrid energy system, Proc., 2017 American Nuclear Society Winter Meeting, 29 October-02 November, 2017, Washington, D. C.
<p>
17. R. A. Borrelli, M. Tolman, J. Lee, Preliminary analysis of facility design for pyroprocessing safeguardability, Proc., 2017 American Nuclear Society Annual Meeting, 11-15 June, 2017, San Francisco, California.
<p>
16. E. Redfoot, R. A. Borrelli, Nuclear fuel cycle simulator as a means to model a nuclear hybrid energy system, Proc., 2017 American Nuclear Society Annual Meeting, 11-15 June, 2017, San Francisco, California.
<p>
15. J. Peterson, M. Haney, R. A. Borrelli, Cybersecurity vulnerability assessment methodologies for nuclear power plants, Proc., 2017 American Nuclear Society Annual Meeting, 11-15 June, 2017, San Francisco, California.
<p>
14. R. A. Borrelli, M. Tolman, Development of a discrete event simulation model for pyroprocessing safeguardability, Proc., 2016 American Nuclear Society Winter Meeting, 06-10 November, 2016, Las Vegas, Nevada.
<p>
13. R. A. Borrelli, Summary of modeling studies in the high reliability safeguards approach, Proc., 2013 American Nuclear Society Winter Meeting, 10-14 November, 2013, Washington, D. C.
<p>
12. R. A. Borrelli, Applying curium spontaneous fission neutrons in the high reliability safeguards approach for remotely-handled nuclear facilities, Proc., Global 2013: International Nuclear Fuel Cycle Conference, 29 September - 03 October, 2013, Salt Lake City, Utah.
<p>
11. R. A. Borrelli, Applying curium spontaneous fission neutrons in the high reliability safeguards approach for remotely-handled nuclear facilities, Proc., 9th International Conference on Facility Operations-Safeguards Interface, 23-27 September, 2012, Savannah, Georgia.
<p>
10. R. A. Borrelli, Role of neutron detection in the high reliability safeguards approach, Proc., International Conf., High-Level Radioactive Waste Management, 10-14 April 2011, Albuquerque, New Mexico.
<p>
9. R. A. Borrelli, Lance Kim, Edward D. Blandford, Yongsoo Hwang, Eung Ho Kim, Per F. Peterson, High reliability safeguards for remote-handled nuclear materials, Proc., 2010 International Congress on Advances in Nuclear Power Plants (ICAPP ‘10) 13-17 June, 2010, San Diego, California.
<p>
8. R. A. Borrelli, Joonhong Ahn, Parametric studies on confinement of radionuclides in the excavated damaged zone due to bentonite type and temperature change, Proc., Clays in Natural & Engineered Barriers for Radioactive Waste Confinement, 4th International Meeting, 29 March - 01 April 2010, Nantes France.
<p>
7. R. A. Borrelli, Olivier Thivent, Joonhong Ahn, Effect of temperature change on bentonite extrusion and radionuclide migration in the excavated damaged zone, Proc., Impact of Thermo-Hydro-Mechanical-Chemical Processes on the Safety of Underground Repositories Conference, 29 September-01 October 2009, Luxembourg.
<p>
6. R. A. Borrelli, Olivier Thivent, Joonhong Ahn, Parametric studies for temperature changes of bentonite extrusion and impacts on radionuclide migration in the excavated damaged zone, Proc., 12th International Conference on the Chemistry and Migration Behaviour of Actinides and Fission Products in the Geosphere, 20-25 September, 2009, Kennewick, Washington.
<p>
5. R. A. Borrelli, Joonhong Ahn, Impact of bentonite extrusion on radionuclide migration in a saturated planar fracture, Proc., 2008 Annual Meeting of the Atomic Energy Society of Japan, 26-28 March 2008, Osaka Japan.
<p>
4. R. A. Borrelli, Joonhong Ahn, Impact of bentonite extrusion on radionuclide in a saturated planar fracture, Proc., Clays in Natural & Engineered Barriers for Radioactive Waste Confinement, 3rd International Meeting, 17-20 September 2007, Lille France.
<p>
3. R. A. Borrelli, Joonhong Ahn, Radionuclide transport in a water-saturated planar fracture with bentonite extrusion, in: Proc., Transport Behavior in Heterogeneous Polymeric Materials and Composites, Mater. Res. Soc. Symp., J. Grunlan, D. Bhattacharyya, E. Marand, O. Regev, A. Balazs (eds.), 1006E, Warrendale, Pennsylvania (2007).
<p>
2. R. A. Borrelli, Joonhong Ahn, Bentonite extrusion in planar fracture based on net water flow, Proc., International Conf., High-Level Radioactive Waste Management, 30 April - 04 May, 2006, Las Vegas, Nevada.
<p>
1. Leo M. Bobek, R. A. Borrelli, PLC-based reactivity measurements using inverse point kinetics, Transactions of the American Nuclear Society, 74, Annual meeting of the American Nuclear Society, 16-20 June, 1996, Reno, Nevada.
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# Articles
R. A. Borrelli, [The USA-ROK 123 Agreement](http://npwg.berkeley.edu/blog/the-usa-rok-123-agreement/), [The Midnight Watch](http://npwg.berkeley.edu/blog/category/the-midnight-watch/). 23 November 2014.
___
# Non-refereed technical reports
<p>
15. J. Seth Dustin, R. A. Borrelli, High level examination of Am-241 as an alternative fuel source in radioisotope thermoelectric generators, LA-UR-20-20574 (2020).
<p>
14. R. A. Borrelli, Richard N. Christensen, Brian Jaques, Samuel Pedersen, Winfred Sowah, Modeling and design of borated aluminum cask for used fuel cooling, Idaho Global Entrepreneurial Mission Final Report, APP-002714 (2019).
<p>
13. R. A. Borrelli, Richard N. Christensen, Brian Jaques, Samuel Pedersen, Winfred Sowah, Modeling and design of borated aluminum cask for used fuel cooling, Idaho Global Entrepreneurial Mission Progress Report, APP-002714 (2018).
<p>
12. Joonhong Ahn, R. A. Borrelli, Esra Orucoglu, Bret P. van den Akker, Seung Min Woo, and Jihae Yoon, Systems assessment for advanced nuclear fuel cycle: Final report for UCBNE-KAERI collaboration, UCBNE-5150 (2015).
<p>
11. J. Ahn, R. A. Borrelli, J. Yoon, Systems assessment for advanced nuclear fuel cycle: Fourth year report for UCBNE-KAERI collaboration, UCB-NE-5137, (2012).
<p>
10. S. Hecker, E. Blandford, A. Hanson, T. Isaacs, N. Milonopoulos, J. Ahn, R. A. Borrelli, J. Choi, L. Kim, P. F. Peterson, J. Yoon, Scientific and institutional aspects of advanced systems for spent nuclear fuels in emerging nuclear countries: Final report, UCB-NE-5135, (2012).
<p>
9. J. Ahn, R. A. Borrelli, L. Kim, P. F. Peterson, J. Yoon, J. Choi, Systems assessment for advanced nuclear fuel cycle: Third year report for UCBNE-KAERI collaboration, UCB-NE-5134, (2011).
<p>
8. J. Ahn, R. A. Borrelli, L. Kim, P. F. Peterson, J. L. Vujic, J. Yoon, J. Choi, Y. S. Hwang, Systems assessment for advanced nuclear fuel cycle: Second year report for UCBNE-KAERI collaboration, UCB-NE-5133, (2010).
<p>
7. Joonhong Ahn, P. F. Peterson, R. A. Borrelli, Lance Kim, Jihae Yoon, Scientific and institutional aspects of advanced systems for spent nuclear fuels in emerging nuclear countries: Interim report, UCB-NE-5130, (2010).
<p>
6. R. A. Borrelli, Olivier Thivent, Joonhong Ahn, Numerical simulation of radionuclide transport in the near field region: Third year report for UCBNE-KAERI collaboration, UCB-NE-5128, (2010).
<p>
5. J. Ahn, E. Blandford, R. A. Borrelli, E. H. Kim, L. Kim, P. F. Peterson, J. L. Vujic, J. Yoon, J. Choi, Y. S. Hwang, Systems assessment for advanced nuclear fuel cycle: First year report for UCBNE-KAERI collaboration, UCB-NE-5126, (2009).
<p>
4. R. A. Borrelli, Joonhong Ahn, Radionuclide transport coupled with bentonite extrusion in a saturated planar fracture: TRIBEX manual, UCB-NE-5111, (2007).
<p>
3. R. A. Borrelli, Joonhong Ahn, Modeling and simulation of bentonite extrusion in a saturated planar fracture, UCB-NE-5110, (2007).
<p>
2. R. A. Borrelli, Joonhong Ahn, Modeling and simulation of radionuclide transport in a saturated planar fracture with bentonite extrusion, UCB-NE-5109, (2007).
<p>
1. Joonhong Ahn, Paul L. Chambré, Daisuke Kawasaki, R. A. Borrelli, Development of integrated repository performance assessment models, UCB-NE-5103, (2006).
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___
# Conference presentations
<p>
31. J. Richards, R. A. Borrelli, Development of a tool for evaluating nuclear integrated energy systems profitability for existing reactors, Proc., Proc., American Nuclear Society Virtual Winter Meeting, 16-19 November, 2020.
<p>
30. *Samuel Cutler, Allysa Bateman, Brenden Heidrich, R. A. Borrelli, James Simpson, Brian J. Jaques, Modeling shielding designs for the safe operation of neutron generators, Idaho Conference on Undergraduate Research, 23-24 July, 2020, Boise, Idaho [_poster_].
<p>
29. *J. Peterson, M. Haney, R. A. Borrelli, An overview of methodologies for cybersecurity vulnerability assessments conducted at nuclear power plants, Proc., American Nuclear Society Winter Meeting, 17-21 November, 2019, Washington, D. C.
<p>
28. *C. Kolias, R. A. Borrelli, D. Barbara, A. Stavrou, Malware detection in critical infrastructures by using the electromagnetic emissions of PLCs, Proc., American Nuclear Society Winter Meeting, 17-21 November, 2019, Washington, D. C.
<p>
27. *J. Peterson, R. A. Borrelli, D. Roberson, Informing electrical grid policy with a nuclear power plant simulator, Energy Policy Research Conference 2019, 29 September - 01 October, 2019, Boise Idaho [_poster_].
<p>
26. *J. Christensen, R. A. Borrelli, C. S. Henkel, B. Matthews, Minimum accident of concern for uranyl sulfate solutions, Proc., American Nuclear Society Annual Meeting, 09-13 June, 2019, Minneapolis, Minnesota.
<p>
25. *R. A. Borrelli, Updates on borated aluminum cask design for onsite used fuel storage, Proc., American Nuclear Society Annual Meeting, 09-13 June, 2019, Minneapolis, Minnesota.
<p>
24. T. MacLean, *M. Haney, R. A. Borrelli, Cybersecurity modeling of non-critical nuclear power plant instrumentation, Proc., Thirteenth Annual IFIP WG 11.10 International Conference on Critical Infrastructure Protection, 11-13 March, 2019, Arlington, Virginia.
<p>
23. *Kathryn D. Huff, Neal Davis, Paul Wilson, R. A. Borrelli, Steven Skutnik, Anthony Scopatz, Jenny Amos, Open-source curriculum development. Academy for Excellence in Engineering Education Strategic Instructional Innovation Program at the University of Illinois, 19 April 2018 [_poster_].
<p>
22. *J. Lee, R. A. Borrelli, Upgrades on high reliability safeguards model for material throughput in fuel fabrication, Proc., American Nuclear Society Annual Meeting, 17-21 June, 2018, Philadelphia, Pennsylvania.
<p>
21. *R. A. Borrelli, J. S. Dustin, Samuel Pedersen, Brian J. Jaques, [Design of a borated aluminum cask design for onsite used fuel storage,](../research-presentations/2018/american-nuclear-society/summer-philadelphia/1-igem-neutron-shielding-analysis-engineering-design.html) American Nuclear Society Annual Meeting, 17-21 June, 2018, Philadelphia, Pennsylvania.
<p>
20. *R. A. Borrelli, Mark S. Delligatti, [Regulatory licensing pathway for a borated aluminum cask design for onsite used fuel storage,](../research-presentations/2018/american-nuclear-society/summer-philadelphia/2-igem-regulatory-analysis.html) Proc., American Nuclear Society Annual Meeting, 17-21 June, 2018, Philadelphia, Pennsylvania.
<p>
19. *J. S. Dustin, R. A. Borrelli, Preliminary Performance Assessment of Americium-241 as Fuel in Radioisotope Thermoelectric Generators for Deep Space Exploration, Proc., ANS NETS 2018 - Nuclear and Emerging Technologies for Space, 26 February - 01 March, 2018, Las Vegas, Nevada.
<p>
18. *J. Lee, R. A. Borrelli, Hazard and operability analysis of a pyroprocessing facility, Proc., 2017 American Nuclear Society Winter Meeting, 29 October-02 November, 2017, Washington, D. C.
<p>
17. *E. Redfoot, K. Verner, R. A. Borrelli, Applying preliminary hazard analysis and analytic hierarchy process to a nuclear renewable hybrid energy system, Proc., 2017 American Nuclear Society Winter Meeting, 29 October-02 November, 2017, Washington, D. C.
<p>
16. *J. Lee, M. Tolman, R. A. Borrelli, Preliminary analysis of facility design for pyroprocessing safeguardability, Proc., 2017 American Nuclear Society Annual Meeting, 11-15 June, 2017, San Francisco, California.
<p>
15. *E. Redfoot, R. A. Borrelli, Nuclear fuel cycle simulator as a means to model a nuclear hybrid energy system, Proc., 2017 American Nuclear Society Annual Meeting, 11-15 June, 2017, San Francisco, California.
<p>
14. *J. Peterson, M. Haney, R. A. Borrelli, Cybersecurity vulnerability assessment methodologies for nuclear power plants, Proc., 2017 American Nuclear Society Annual Meeting, 11-15 June, 2017, San Francisco, California.
<p>
13. *M. Tolman, J. Lee, R. A. Borrelli, Development of a discrete event simulation model for pyroprocessing safeguardability, Proc., 2016 American Nuclear Society Winter Meeting, 06-10 November, 2016, Las Vegas, Nevada.
<p>
12. *R. A. Borrelli, Summary of modeling studies in the high reliability safeguards approach, 2013 American Nuclear Society Winter Meeting, 10-14 November 2013, Washington, D. C.
<p>
11. *R. A. Borrelli, Applying curium spontaneous fission neutrons in the high reliability safeguards approach for remotely-handled nuclear facilities, Global 2013: International Nuclear Fuel Cycle Conference, 29 September - 03 October, 2013, Salt Lake City, Utah.
<p>
10. *R. A. Borrelli, Applying curium spontaneous fission neutrons in the high reliability safeguards approach for remotely-handled nuclear facilities, 9th International Conference on Facility Operations-Safeguards Interface, 23-27 September, 2012, Savannah, Georgia.
<p>
9. *R. A. Borrelli, Role of neutron detection in the high reliability safeguards approach, International Conf., High-Level Radioactive Waste Management, 10-14 April 2011, Albuquerque, New Mexico.
<p>
8. *R. A. Borrelli, Lance Kim, Edward D. Blandford, Yongsoo Hwang, Eung Ho Kim, Per F. Peterson, High reliability safeguards for remote-handled nuclear materials, International Congress on Advances in Nuclear Power Plants (ICAPP ‘10), 13-17 June, 2010, San Diego, California.
<p>
7. *R. A. Borrelli, Joonhong Ahn, Parametric studies on confinement of radionuclides in the excavated damaged zone due to bentonite type and temperature change, Clays in Natural & Engineered Barriers for Radioactive Waste Confinement, 4th International Meeting, 29 March - 01 April 2010, Nantes France. [_poster_]
<p>
6. R. A. Borrelli, *O. Thivent, J. Ahn, Effect of temperature change on bentonite extrusion and radionuclide migration in the excavated damaged zone, Impact of Thermo-Hydro-Mechanical-Chemical Processes on the Safety of the Underground Repositories Conference, 29 September - 01 October 2009, Luxembourg.
<p>
5. *R. A. Borrelli, Olivier Thivent, Joonhong Ahn, Parametric studies for temperature changes of bentonite extrusion and impacts on radionuclide migration in the excavated damaged zone, 12th International Conference on the Chemistry and Migration Behaviour of Actinides and Fission Products in the Geosphere, 20-25 September, 2009, Kennewick, Washington. [poster]
<p>
4. *R. A. Borrelli, Joonhong Ahn, Impact of bentonite extrusion on radionuclide migration in a saturated planar fracture, Annual Meeting of the Atomic Energy Society of Japan, 26-28 March 2008, Osaka Japan.
<p>
3. *R. A. Borrelli, Joonhong Ahn, Impact of bentonite extrusion on radionuclide migration in a saturated planar fracture, Clays in Natural & Engineered Barriers for Radioactive Waste Confinement, 3rd International Meeting, 17-20 September, 2007, Lille France.
<p>
2. *R. A. Borrelli, J. Ahn, Radionuclide transport in a water-saturated planar fracture with bentonite extrusion, Transport Behavior in Heterogeneous Polymetric Materials and Composites, Mater. Res. Soc. Symp., J. Grunlan, D. Bhattacharyya, E. Marand, O. Regev, A. Balazs (eds.), 1006E, 2007, San Francisco, California.
<p>
1. *R. A. Borrelli, Joonhong Ahn, Bentonite extrusion in planar fracture based on net water flow, International Conf., High-Level Radioactive Waste Management, 30 April - 04 May, 2006, Las Vegas, Nevada.
___
# Teaching experience
**University of Idaho, Idaho Falls, College of Engineering, Nuclear Engineering Program**
**Assistant Professor**
*NE502: Heterogeneity comparisons of intermediate enrichment uranium in critical systems (directed study)*
The ICSBEP handbook contains descriptions and evaluations of critical experiments conducted in facilties throughout the world. The reach of the handbook stretches to the beginning of the history of nuclear engineering. As part of that history, a number of critical experiments have been conducted using arrays of fissile material in the intermediate enrichment range, which is defined for the purposes of this course as ten to forty percent (10%-40%). In those evaluations, a variety of methods have been discussed and described which convert a system of known or unknown degree of heterogeneity into a simplified homogeneous model, which is a traditional method for examining the critical characteristics of multiplying systems. The specific methodology for this conversion varies between evaluations and is explained in some cases, where other cases are less descriptive. It is of interest to the field of nuclear criticality safety to improve the understanding of the effect of heterogeneity on the critical characteristics of multiplying fissile systems, particularly in the range of intermediate enrichment. It is of further interest to the field that a methodology be established which can be used to evaluate these types of systems for practical nuclear criticality safety applications, especially the development of nuclear criticality safety limits.
*Fall 2020*
**University of Idaho, Idaho Falls, College of Engineering, Nuclear Engineering Program**
**Assistant Professor**
*NE502: Computation of minimum spherical critical volume for nuclear criticality safety applications (directed study)*
The nuclear safety guide, Critical Dimensions of Systems Containing U-235, Pu-239, and U-233 contains a graph of minimum critical volumes as a function of U-235 enrichment in homogeneous and heterogeneous hydrogen-moderated systems. This graph includes a wide extrapolation between the data for ten percent enrichment and ninety-three percent enrichment. A similar graph appears in Anomalies of Nuclear Criticality without the extrapolation. This graph shows a clear transition at approximately thirty-five percent enrichment between two different types of systems. It is clear that there is a difference between the extrapolated minimum spherical critical volumes and the calculated critical volumes. As part of the development of nuclear criticality safety methodology for intermediate-enrichment uranium systems, it is necessary to more fully evaluate and explain the nature of the transition point. This work will attempt to re-create and expand on the data used to produce this graph and more fully evaluate the nature of the minimum critical volume for intermediate-enrichment systems. The secondary objective will be the proposal of nuclear criticality safety rules which could be applied to these data to ensure that fissionable material operations in this range of enrichment can be conducted safely.
*Fall 2020*
**University of Idaho, Idaho Falls, College of Engineering, Nuclear Engineering Program**
**Assistant Professor**
*NE502: Subcritical multiplication (directed study)*
Using published fundamental nuclear data for thermal neutrons, this course will examine the relationship between processes of fission and capture and develop models for reactivity worth as a function of thermal fission and capture cross-sections and local thermal flux. This course will include evaluation of tests in zero-power reactors. The Advanced Test Reactor (ATR) physics analyses rely heavily on measurement results from the Advanced Test Reactor Critical Facility (ATRC). These results are easily delivered in terms of reactivity worth, but the results are almost never directly applicable to ATR due to differences in thermal neutron flux. Reactivity worth is not a fundamental property of a material and indeed is not a characteristic property of a given piece of reactor hardware if the hardware is to be irradiated in a new neutron environment. However, translating reactivity worth of a piece of hardware in ATRC to a pair of macroscopic cross-sections essentially characterizes the hardware with constants that will be applicable in any subsequent location in ATR or ATRC. Therefore, reactivity worth in a new irradiation position can be predicted by calculation.
*Fall 2020*
**University of Idaho, Idaho Falls, College of Engineering, Nuclear Engineering Program**
**Assistant Professor**
*NE502: Computation and modeling of nuclear systems (directed study)*
Using published nuclear computational modeling references, this course will examine prior efforts to simplify the neutron transport and depletion calculations for advanced reactor designs, such as high-temperature pebble-bed reactors. These include efforts to model heterogeneous stochastic media, such as TRISO fuel particles dispersed in a graphite matrix. Deterministic neutron transport in stochastic media has resulted in several new methods developed in order to address the challenges associated with modeling them, however, comparison of the proposed and implemented methods has been largely absent. Other challenges facing the modeling of pebble-bed reactors include the depletion calculations for individual pebbles. Because of the flow of pebbles through the core, and the recirculation of said pebbles in most modern designs, the depletion of individual pebbles can affect the criticality of the system as well as the temperature profile of individual pebbles, which was demonstrated to have significant safety implications based on the operation of the German AVR pebble-bed system. To these ends, this course will identify relevant literature regarding these topics and the feasibility of implementing these methods in modern nuclear modeling tools, such as the Griffin tool in development at Idaho National Laboratory.
*Fall 2020*
**University of Idaho, Idaho Falls, College of Engineering, Nuclear Engineering Program**
**Assistant Professor**
*NE502: Historical examinations of heterogeneity in nuclear criticality safety (directed study)*
Using published nuclear criticality safety references, this course will conduct an examination of the effect of heterogeneity with respect to nuclear criticality safety. As part of the history of nuclear criticality safety, a number of critical experiments have been conducted using arrays of fissile material in an attempt to quantify the effect of heterogeneity in the determination of safe handling limits. In these attempts, a number of low-enriched experiments were examined and converted in their critical dimensions to establish a useful baseline from which other limits could be extrapolated. It is of interest to the field of nuclear criticality safety to improve the understanding of the effect of heterogeneity on the critical characteristics of multiplying fissile systems, particularly in the range of intermediate enrichment. It is of further interest to the field that a methodology be established which can be used to evaluate these types of systems for practical nuclear criticality safety applications, especially the development of nuclear criticality safety limits. To that end, this course will identify relevant data in the literature used to generate historical experiments and apply MCNP to model these experiments in order to understand and evaluate assumptions and restrictions raised in the experiments.
*Spring 2020*
**University of Idaho, Idaho Falls, College of Engineering, Nuclear Engineering Program**
**Assistant Professor**
*NE502: Heterogeneity comparisons of intermediate enrichment uranium in critical systems (directed study)*
Using the International Criticality Safety Benchmark Evaluation Project (ICSBEP) handbook of evaluated critical experiments, conduct an examination of the effect of heterogeneity in intermediate-enrichment uranium systems. The ICSBEP handbook contains descriptions and evaluations of critical experiments conducted in facilities throughout the world. The reach of the handbook stretches to the beginning of the history of nuclear engineering. In those evaluations, a variety of methods have been discussed and described which convert a system of known or unknown degree of heterogeneity into a simplified homogeneous model, which is a traditional method for examining the critical characteristics of multiplying systems. The specific methodology for this conversion varies between evaluations and is explained in some cases, where other cases are less descriptive. It is of interest to the field of nuclear criticality safety to improve the understanding of the effect of heterogeneity on the critical characteristics of multiplying fissile systems, particularly in the range of intermediate enrichment. It is of further interest to the field that a methodology be established which can be used to evaluate these types of systems for practical nuclear criticality safety applications, especially the development of nuclear criticality safety limits. This course will identify and evaluate relevant benchmark experiments for heterogeneity effects using MCNP to establish new baseline models from the benchmark handbook.
*Spring 2020*
**University of Idaho, Idaho Falls, College of Engineering, Nuclear Engineering Program**
**Assistant Professor**
*NE502: Nuclear integrated energy systems (directed study)*
Nuclear renewable hybrid energy systems enable a nuclear reactor to load follow with a renewable energy source. These must be designed to distribute energy dynamically by supplying electricity to the grid while using either thermal or electrical energy for industrial applications. This takes advantage of the flexible distribution of electricity or heat to maximize profit. The industrial process serves as a load sink for the excess heat or electricity produced by the nuclear reactor. Economic challenges to the current United States nuclear light water reactor (LWR) fleet have led to early plant closures. While LWRs primarily deliver baseload electricity, there is no reason why nuclear energy produced by these reactors cannot be used to provide energy to a range of industrial applications. This directed study course will identify feasible systems, products, and commodities that could be produced by existing nuclear plants. As part of this, cost and potential profitability will be analyzed within the context of market structures and grid reliability.
*Spring 2020*
**University of Idaho, Idaho Falls, College of Engineering, Nuclear Engineering Program**
**Assistant Professor**
*NE527: Nuclear material storage, transport, disposal*
There is a wide range of nuclear materials that are stored, transported and disposed of each day. The materials include medical radioisotopes, new fuel pellets, used fuel, and industrial radioisotopes. This course will cover the regulations that govern nuclear material storage, transportation and disposal, as well as the engineering requirements and practical aspects of handling these materials.
*Spring 2020*
**University of Idaho, Idaho Falls, College of Engineering, Nuclear Engineering Program**
**Assistant Professor**
*NE535: Nuclear Criticality Safety I*
This course applies uses the foundation of applied nuclear physics to develop and explain the international and domestic rules and practices that are used to prevent inadvertent criticality in fuel cycle applications such as spent fuel storage and processing.
*Spring 2020*
**University of Idaho, Idaho Falls, College of Engineering, Nuclear Engineering Program**
**Assistant Professor**
*NE585: Nuclear Fuel Cycle Analysis*
This course presents the nuclear fuel cycle can as an holistic system with components related in many complex ways and focuses on systems analysis of components that comprise the nuclear fuel cycle to understand the contemporary challenges facing nuclear energy.
*Fall 2017*
**University of Idaho, Idaho Falls, College of Engineering, Nuclear Engineering Program**
**Assistant Professor**
*TM529: Risk Assessment*
This course is designed to provide students with an understanding of how to perform a comprehensive risk assessment applicable to a wide variety of engineering problems in many different disciplines. The course will focus on failure mode and effect analysis, fault tree analysis, probabilistic risk analysis, and human reliability analysis. The course will also cover fundamental probability and statistics content.
*Spring 2021; 2019; 2018; 2017; 2016*
**University of Idaho, Idaho Falls, College of Engineering, Nuclear Engineering Program**
**Assistant Professor**
*NE450: Principles of Nuclear Engineering*
In this course, an overview of fundamental nuclear engineering principles and how these are practically applied to contemporary, nuclear engineering problems will be presented. The topics covered in this course include: nuclear physics and reactions, materials science, radiation protection, energy production, fuel cycle analysis, advanced reactor design, fusion, nonproliferation, back-end management, and risk assessment and safety. Throughout the course, the ethical considerations with regards to engineering problems within these fields will also be discussed.
*Fall 2019; 2018; 2017; 2016; 2015*
**Diablo Valley College, Department of Architecture and Engineering**
**Adjunct Professor**
*ENGIN110: Introduction to Engineering*
This course introduces students to fundamental engineering principles. Students learn how these are applied to contemporary engineering problems through laboratory exercises, homework assignments, design projects, interviews with professional engineers, and field trips to engineering companies. Topics include: materials science, risk assessment and safety, critical problem-solving, engineering analysis, engineering design processes, project development, engineering software, and
presentation tools. The role of the engineer in society, professionalism, and engineering ethics are major themes. The emphasis is on creative problem-solving, teamwork, and effective communication, both in presentation and writing.
*Spring 2015; 2014; 2013; Fall 2014*
**University of California-Berkeley, Department of Nuclear Engineering**
**Instructor**
*NE92: Issues in Nuclear Science and Engineering*
This course provides undergraduate students with an overview of the nuclear engineering profession, including fundamental nuclear engineering principles and how these are practically applied to nuclear engineering problems. The topics covered include nuclear physics and reactions, materials science, radiation protection, energy production, fuel cycle analysis, advanced reactor design, fusion, nonproliferation, back-end management, risk assessment, and safety. Throughout the course, the ethical considerations concerning engineering problems within these fields are also addressed through a comprehensive, student-driven course project.
*Fall 2011*
**University of California-Berkeley, Department of Nuclear Engineering**
**Instructor**
*NE375: Teaching Techniques in Nuclear Engineering*
This course acquaints graduate student instructors (GSIs) with teaching techniques for courses in the Department of Nuclear Engineering. The GSI will have several duties far beyond grading assignments and/or examinations: conducting discussion sessions, review lectures, or laboratory experiments. The GSI, therefore, needs to develop the appropriate tools to use when facing these pedagogical challenges. Three students from the 2010 course received the Outstanding Graduate Student Instructor Award given by the UC-Berkeley Graduate Student Instructor Teaching & Resource Center.
*Fall 2011; 2010*
**The University of Tokyo, Department of Nuclear Engineering/Management**
**Part time lecturer**
*Technical English for Scientists*
This course provided the opportunity for non-native English speaking students to develop technical communication skills; i.e., presenting scientific and technical material to an informed audience at an international conference. In this course, the ‘assertion evidence design’ concept for technical presentation of scientific topics was applied to student research interests. Transmutable skills focused on the professional communication of scientific research in various public speaking
formats and a comfortable familiarity with the English language to establish a stronger foundation for technical writing.
*Winter, Summer 2008; Winter 2007*
___
# Related teaching experience
**University of California-Berkeley, Department of Nuclear Engineering**
**Graduate Student Instructor**
*NE375: Teaching Techniques in Nuclear Engineering*
Coordinated guest lecturers from departments within the College of Engineering
Prepared lectures for effective teaching strategies for the undergraduate classroom
Assessed individual student technical presentations and overall course grading
*Fall 2006*
*E124: Ethics and the Impact of Technology on Society*
Conducted multiple discussion sections on a weekly basis and review lectures
Supervised research projects based on current, ethical and scientific issues
Assessed individual student presentations, projects, and overall course grading
*Spring 2006; 2005; 2004*
*IDS110: Introduction to Computing*
Conducted multiple laboratory sessions on a weekly basis
Supervised undergraduate research projects focused on web based education
Assessed laboratory assignments and project grading
*Fall 2004*
*NE92: Issues in Nuclear Science and Engineering*
Coordinated guest lecturers from Department of Nuclear Engineering
Conducted review lectures
Developed examinations and homework assignments
Assessed overall course grading
*Spring 2002; 2000*
*NE275: Principles and Methods of Risk Analysis*
This graduate course requires a deeper understanding of the subject matter, due to the student body. The course was one of three in the curriculum with the highest credit load. The main responsibility in this was to advise and grade semester projects and presentations based on risk assessments of engineering systems.
*Fall 2001*
**University of California-Berkeley, Department of Nuclear Engineering**
**Reader**
NE150: Introduction to Nuclear Reactor Theory - *Spring 2003*
NE104: Radiation Detection and Nuclear Instrumentation Laboratory - *Fall 2002*
NE107: Introduction to Imaging - *Spring 2001*
NE120: Nuclear Materials - *Fall 2000*
Supervised laboratory sessions
Assessed examinations, homework assignments, laboratory reports, final grades
Conducted review lectures
___
# Professional service
**University of Idaho**
Chair - Third Year Promotion & Tenure, Department of Nuclear Engineering and Industrial Management
*2021*
Organizer - NNSA Fellowship Information Symposia
*2017-21*
Organizer - American Nuclear Society Graduate School Fair
*2020*
Faculty Advisor - American Nuclear Society, University of Idaho Student Section
Member - Graduate Faculty, University of Idaho
Member - NRC Student Fellowship Oversight Committee, Nuclear Engineering Program
Member - Nuclear Engineering Program Admissions Committee
**Faculty search committees**
Nuclear Engineering, Idaho State University, Idaho Falls Polytechnic Institute
*2018*
Mechanical/Nuclear Engineering, University of Idaho
*2017*
**Peer reviewer**
American Nuclear Society - Annual and Winter Meetings
IEEE Transactions on Nuclear Science
American Nuclear Society Fuel Cycle and Waste Management Division John Randall Scholarship
External reviewer - Khalifa University of Science and Technology
Nuclear Science User Facilities
Advances in Engineering Software
Nuclear Engineering and Techology
Annals of Nuclear Energy
Progress in Nuclear Energy
Energy Science & Engineering
Nuclear Engineering and Design
International Journal of Nuclear Energy
John Wiley & Sons, Inc.
2020 U.S. Department of Energy, Small Business Innovation Research/Small Business Technology Transfer Programs Phase I Release 2
2019 American Nuclear Society - Global Topical Conference
2019 American Nuclear Society Student Conference, Virginia Commonwealth University
2019 Idaho High School Essay Contest, sponsored by Idaho Section, American Nuclear Society
2018 Idaho High School Essay Contest, sponsored by Idaho Section, American Nuclear Society
2018 U.S. Department of Energy, Small Business Innovation Research/Small Business Technology Transfer Programs Phase I Release 2
2018 American Nuclear Society Student Conference, University of Florida
2017 Idaho High School Essay Contest, sponsored by Idaho Section, American Nuclear Society
2017 U.S. Department of Energy, Small Business Innovation Research/Small Business Technology Transfer Programs Phase II Release 2
2017 U.S. Department of Energy, Small Business Innovation Research/Small Business Technology Transfer Programs Phase II Release 1
2017 Department of Energy, Office of Nuclear Energy, Consolidated Innovative Nuclear Research FOA
2017 American Nuclear Society Student Conference, University of Pittsburgh
2016 Idaho High School Essay Contest, sponsored by Idaho Section, American Nuclear Society
2016 U.S. Department of Energy, Small Business Innovation Research/Small Business Technology Transfer Programs Phase I Release 2
FY17 TI Portfolio, Bonneville Power Administration, Office of Technology Innovation
2016 American Nuclear Society Student Conference, University of Wisconsin-Madison
2015 Idaho High School Essay Contest, sponsored by Idaho Section, American Nuclear Society
FY16 TI Portfolio, Bonneville Power Administration, Office of Technology Innovation
U.S. Department of Energy, Advanced Research Projects Agency-Energy, Concept Papers, Open 2015 FOA
U.S. Department of Energy, Advanced Research Projects Agency-Energy, Review Panel, 08-10 August 2012, Arlington, Virginia.
International Conf., High-Level Radioactive Waste Management, 10-14 April 2011, Albuquerque, New Mexico.
Clays in Natural & Engineered Barriers for Radioactive Waste Confinement, 4th International Meeting, 29 March - 01 April 2010, Nantes France.
Clays in Natural & Engineered Barriers for Radioactive Waste Confinement, 3rd International Meeting, 17-20 September, 2007, Lille France.
**Conference committees**
Technical Program Committee, International High-Level Radioactive Waste Management Conference, 14-18 April, 2019, Knoxville, Tennessee.
Co-chair, Technical Program Committee, 2018 Advances in Nuclear Nonproliferation Technology and Policy Conference, American Nuclear Society, 11-15 November, 2018, Orlando, Florida.
Technical program committee, Advances in Nuclear Nonproliferation Technology and Policy Conference: Bridging the Gaps in Nuclear Nonproliferation, 25-30 September, 2016, Santa Fe, New Mexico.
Technical program paper review committee, Advances in Nuclear Nonproliferation Technology and Policy Conference: Bridging the Gaps in Nuclear Nonproliferation, 25-30 September, 2016, Santa Fe, New Mexico.
**Technical session organizer**
Cybersecurity for nuclear installations, American Nuclear Society Winter Meeting, 17-21 November, 2019, Washington, D. C. (_co_Organizer with Prof. Jamie B. Coble, University of Tennessee-Knoxville_)
**Technical session chair**
Spent fuel storage and transportation, American Nuclear Society Winter Meeting, 17-21 November, 2019, Washington, D. C.
Cybersecurity for nuclear installations, American Nuclear Society Winter Meeting, 17-21 November, 2019, Washington, D. C.
Data synthesis for pyroprocessing safeguards, 2018 Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), American Nuclear Society, 11-15 November, 2018, Orlando Florida.
Special session - Prof. J. Ahn, International High-Level Radioactive Waste Management Conference, 09-13 April, 2017, Charlotte, North Carolina.
Nonproliferation policy, concepts, and approaches: Treaty verification regimes, state-level concepts and fuel cycle analysis, Advances in Nuclear Nonproliferation Technology and Policy Conference: Bridging the Gaps in Nuclear Nonproliferation, 25-30 September, 2016, Santa Fe, New Mexico.
Security, safeguards, and non-proliferation, International Conf., High-Level Radioactive Waste Management, 10-14 April 2011, Albuquerque, New Mexico.
Used Fuel recycling technologies-I, International Congress on Advances in Nuclear Power Plants (ICAPP ‘10) 13-17 June, 2010, San Diego, California.
Engineered systems and transport processes, International Conf., High-Level Radioactive Waste Management, 07-11 September, 2008, Las Vegas, Nevada.
Challenges in nuclear waste disposal: Sociological aspects and technical approaches, Global Center of Excellence, 06 December, 2007, The University of Tokyo, Tokyo Japan.
**Panels**
Think open fellowship at the University of Idaho, Idaho Open Education Week, 01-05 March 2021 _virtual_
Think Open Fellows at the University of Idaho is an open incubator program that awards 6 fellowships each year to support faculty and graduate students in transitioning a course from a standard text to open or extremely low cost course materials. To date, this program has saved students over \$300,000 while also encouraging innovation. This panel session with current and past fellows will discuss the Think Open Fellows program including design and implementation details, previous and current Think Open Projects, and tips for implementing a program at your institution.
**Workshop participant**
Taking Care of You: Student-Mentor Relationships, American Nuclear Society Student Conference, 08-10 April 2021 _virtual_
A great mentoring situation can pave the way for success out of undergraduate or graduate school. Likewise, a poor or unhealthy mentoring relationship can cause lasting negative consequences on the students. Many times these interactions go undiscussed, and one goal of this workshop is to empower students to talk about and take charge of unhealthy mentoring relationships. This student and faculty-led workshop will explore multiple facets of this relationship, including how to identify the right mentor for you, what it means to maintain a good student-mentor relationship, how to identify unhealthy situations, and what resources are available to students who may find themselves in such situations. This workshop will include panel discussion, small-group discussion, panelist-led role-playing, and an open Q&A.
**Invited talks**
*International Atomic Energy Agency*
*virtual*
Best practices at the University of Idaho
Knowledge Management Assist Visits for Nuclear and Radiological Education and Training Providers
*July 2021*
*University of Idaho - Idaho Falls Center for Higher Education*
Strategies and success for ethical research
Vandal Advantage Graduate Student Orientation
*August 2019; 2018*
*Seminars*
University of Tennesee-Knoxville Department of Nuclear Engineering
*October 2019*
*Lightning talks*
Center for Advanced Energy Studies - Idaho National Laboratory Nuclear Science and Technology Collaborative Research Planning Meeting
*February 2018*
Center for Advanced Energy Studies - Idaho National Laboratory National and Homeland Security Science and Technology Collaborative Research Planning Meeting
*February 2018*
Center for Advanced Energy Studies - Idaho National Laboratory Energy & Environment Science and Technology Collaborative Research Planning Meeting
*November 2017*
*Lectures*
Stanford University Pre-Collegiate Summer Institutes, Stanford University, Stanford, California
*July 2014*
___
**Symposia organizer**
Nuclear cybersecurity research initiatives annual meeting, Center for Advanced Energy Studies, 27-28 July, 2017, Idaho Falls, Idaho.
Nuclear cybersecurity research focus area identification annual meeting, Center for Advanced Energy Studies, 21-22 July, 2016, Idaho Falls, Idaho.
Technical implications of nuclear energy system options, Symposium on scientific and institutional aspects of advanced systems for spent nuclear fuels in emerging nuclear countries, Center for International Security and Cooperation, 29-30 September, 2011, Stanford University, Palo Alto, California.
# Community service
**College of Eastern Idaho Machine Tool Technology Advisory Board**
*2018*
**Idaho American Nuclear Society Smoke Detector Donation Program**
Over the past fourteen years, we have worked with more than 70 fire departments to donate more than 5700 smoke detectors to Idaho residents. From 2016-19, we donated nearly 1800 smoke detectors to Arimo, Ashton, Bancroft, Bear Lake, Clear Creek, Declo, Downey, Grace, Hamer, Lava Hot Springs, Roberts, Shelley, and Soda Springs, across southeastern Idaho; Centerville, Clear Creek, Horseshoe Bend, Idaho City, Lowman, Placerville and Valley of the Pines in Boise County; and north to the panhandle in Coeur D'Alene, Mullan, Shoshone, North Side, and West Pend.
*2016-Present*
**Idaho American Nuclear Society Highway Cleanup**
Garbage cleanup of Miles 122-124 on Interstate 15 twice per year
*Spring,Fall - 2016-19*
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# Outreach and professional activities
Utah State University Graduate School Fair
*September 2019*
Montana Tech Career Fair
*September 2019; March 2018*
American Nuclear Society Diversity Social UI ANS Student Sponsorship
*June 2018; November 2017; June 2017*
UI ANS Symposium on Moscow Campus
*October 2018; March 2017*
Department of Energy consent based siting meeting
*July 2016*
CAES Summer Seminar Series
*May 2016*
PHYSOR UI Sponsorship
*April 2016*
Boise State University Nuclear Research Summit
*March 2016*
American Nuclear Society BYU Student Social
*October 2018; February 2016*
BYUI Career Fair
*October 2015*
___
# Professional training
**International Atomic Energy Agency** _virtual_
**Invited participant**
*Technical Meeting on Knowledge Management Assist Visits for Nuclear and Radiological Education and Training Providers*
This IAEA hosted workshop focused on best practices, for example student recruitment, staff retention, implementation of distance learning or a novel way of teaching a traditional part of a curriculum. This also included engaging industry for outreach programs or getting access to online facilities.
**Virtual**
**Invited participant**
*Defense Established Program to Stimulate Competitive Research (DEPSCoR)*
The Capacity Building opportunity is a new component of DEPSCoR and aims to support the strategic objectives of Institutes of Higher Education in DEPSCoR States/Territories to achieve basic research excellence in areas of high relevance to the DoD. The Virtual DEPSCoR Day will include overviews of the FOAs, various panel sessions and breakout sessions with Program Officers representing the topics in the Research Collaboration FOA.
*June 2021*
**Virtual**
**Invited participant**
*GAIN-EPRI-NEI Advanced Reactors Safeguards & Security Workshop*
The focus of this workshop was to understand how advanced reactors would be able to be licensed under United States domestic safeguards requirements. Participants included academia, industry, and government.
*April 2021*
**Virtual**
**Participant**
*NSF Broader Impacts 101 Workshop*
Proposals submitted to the National Science Foundation (NSF) are evaluated on both their intellectual merit and their broader impacts (BI) - the impacts on and benefits to society of the proposed research. This free workshop is designed for anyone considering applying for funding to the NSF who wishes to increase the competitiveness of their proposals. Participants will develop strategies for designing, implementing, and evaluating BI activities, and will be guided through the process of aligning their BI activities with their research and professional/personal interests to develop a `lifelong' BI identity.
*April 2021*
**Pacific Northwest National Laboratory**
**Invited participant**
*PNNL Lab Day*
Students and faculty from the University of Idaho were invited to Pacific Northwest National Laboratory to learn about the research activities at the laboratory. The day also included hands-on safeguards and security experiments conducted at laboratory facilities, such as materials accounting and vehicle searches.
*May 2019; 2018; 2017*
**Los Angeles**
**Participant**
*National Science Foundation Grant Development Conference*
Key officials representing each NSF program directorate, administrative office, Office of General Counsel, and Office of the Inspector General will participate in this two-day conference. The conference is considered a must, particularly for new faculty, researchers, educators and administrators who want to gain insight into a wide range of important and timely issues at NSF, including: the state of current funding; the proposal and award process; and current and recently updated policies and procedures.
*May 2019*
**University of Illinois Urbana-Champaign**
**Invited participant**
[*Collaborative open source curriculum development*](https://necx-org.github.io/)
This workshop concluded a year of faculty interaction at six universities to develop curricula for courses common across the same disciplines at multiple universities in order to reduce the amount of time that any individual professor spends on creating what is essentially duplicate materials. The method proposed in this workshop is based on open source software development, where code is shared in online repositories, reviewed by peers, and contributed to the main project.
*July 2018*
**Generation Atomic + GAIN - Nuclear Advocacy and Communications Training**
**Facilitator**
Opposition groups repeatedly claim that nuclear power plants are unsafe. Recently, the U.S. nuclear power industry has been characterized as too expensive and dangerous when compared to other energy sources. As members of the nuclear community, we know that the success of nuclear energy has never been more important to ensuring a positive future for the world – but what can we do to make a difference? This workshop will leave participants energized to tell today’s nuclear power story and be well-equipped with the tools to do so. Convincing others about the benefits of nuclear involves more than just laying out the facts. Thoughtful and personal storytelling bridges gaps when speaking those who are unfamiliar with the technology by explaining the personal and moral reasons that we work in this field. Telling our personal stories and motivations for working in nuclear creates common ground from which we can better explain nuclear’s benefits: whether it’s as a mother talking to a father, a surfer talking to a skier, or a cook talking to a conservationist, the human stories that nuclear makes possible are our strongest tools when speaking to the public. The most effective nuclear advocacy takes place at the interpersonal level when we strike up conversations with peers and even better, strangers. Because you can never know who it might be sitting across from you at that dinner party or next to you on the airplane, it’s important to practice having open, considerate conversations with people of all backgrounds.
*June 2018*
**Pacific Northwest National Laboratory**
**Invited participant**
*Cyber Security Course for Safeguards Practitioners*
The course is designed for early to mid-career safeguards practitioners (technical instrument developers, instrument users, policy advisors, etc.) who will benefit from a greater understanding of cyber security threats and how to reduce risks to safeguards systems and processes. This 3.5 day course is designed to teach safeguards and cybersecurity experts how to recognize and mitigate potential cybersecurity vulnerabilities in emerging safeguards instrumentation, information systems, and conduct of operations. This training features classroom style learning opportunities through hands-on exercises and provides plenty of time for questions and discussion. Participants will learn new cyber security skills, use cyber security tools, and collaborate with one another and cyber experts to resolve challenges. They will gain an understanding of cyber security principles and a better awareness of cyber risks associated with safeguards systems. Exercises will include puzzles, exploits of attended and unattended monitoring systems, blended physical and cyber attacks on fictional nuclear facilities, and network defense.
*April 2018*
**Center for Advanced Energy Studies - Idaho National Laboratory Nuclear Science and Technology**
**Invited participant**
*Collaborative Research Planning Meeting*
The Center for Advanced Energy Studies (CAES) is a catalyst for collaborative projects focused on energy research, achieved via connections between the CAES entities – Idaho National Laboratory (INL), Boise State University, Idaho State University, University of Idaho, and University of Wyoming – and beyond. Through a series of strategic planning meetings, CAES leadership aims to develop a set of focused research directions. The meeting is intended to establish new collaboration, along with a list of prioritized goals and actions items that will steer internal research investments with the intent of growing sustainable, externally-funded programs. The planning meeting will focus on a strategic area tied to one or more INL directorates and will bring together the appropriate INL and university leadership and researchers.
*February 2018*
**Center for Advanced Energy Studies - Idaho National Laboratory National and Homeland Security Science and Technology**
**Invited participant**
*Collaborative Research Planning Meeting*
The Center for Advanced Energy Studies (CAES) is a catalyst for collaborative projects focused on energy research, achieved via connections between the CAES entities – Idaho National Laboratory (INL), Boise State University, Idaho State University, University of Idaho, and University of Wyoming – and beyond. Through a series of strategic planning meetings, CAES leadership aims to develop a set of focused research directions. The meeting is intended to establish new collaboration, along with a list of prioritized goals and actions items that will steer internal research investments with the intent of growing sustainable, externally-funded programs. The planning meeting will focus on a strategic area tied to one or more INL directorates and will bring together the appropriate INL and university leadership and researchers.
*February 2018*
**Center for Advanced Energy Studies - Idaho National Laboratory Energy & Environment Science and Technology**
**Invited participant**
*Collaborative Research Planning Meeting*
The Center for Advanced Energy Studies (CAES) is a catalyst for collaborative projects focused on energy research, achieved via connections between the CAES entities – Idaho National Laboratory (INL), Boise State University, Idaho State University, University of Idaho, and University of Wyoming – and beyond. Through a series of strategic planning meetings, CAES leadership aims to develop a set of focused research directions. The meeting is intended to establish new collaboration, along with a list of prioritized goals and actions items that will steer internal research investments with the intent of growing sustainable, externally-funded programs. The planning meeting will focus on a strategic area tied to one or more INL directorates and will bring together the appropriate INL and university leadership and researchers.
*November 2017*
**Idaho Falls Post Register**
**Participant**
*Intermountain Energy Summit*
This summit is held annually and covers energy issues unique to the intermountain region. Participants include faculty from local universities, researchers from national laboratories, energy companies, and politicians. This year, the theme is energy security with a focus on nuclear, renewable, and alternative energy sources and continued advancements in grid and cybersecurity.
*August 2017; 2016; 2015*
**Idaho National Laboratory**
**Project mentor**
*Modeling, Experimentation, Validation (MeV) Summer School*
The MeV Summer School provides enhanced training for engineers and applied scientists involved in design, licensing, and operation of current and advanced nuclear reactor systems through a multi-faceted learning approach of lectures, tours, and hands-on activities. The school is being organized through the cooperation of national laboratories, industry, government agencies, and universities that share the goal of building a strong workforce to support global nuclear expansion. The faculty will be drawn from the top experts in academia, industry, and government. The general organization and conduct of the school will be overseen by an international board of senior experts. A local secretariat will provide technical, logistical and administrative support to students and faculty. It is the aim of the school to foster the development of a next-generation network of scientists and engineers capable of advancing nuclear energy in the 21st century through integrated
modeling and experimentation.
*July 2017*
**University of Illinois Urbana-Champaign**
**Invited participant**
*PyNE Summit*
PyNE is a suite of tools to aid in computational nuclear science and engineering. PyNE seeks to provide native implementations of common nuclear algorithms, as well as Python bindings and I/O support for other industry standard nuclear codes.
*June 2017*
**University of Illinois Urbana-Champaign**
**Invited participant**
*Collaborative open source curriculum development*
This workshop included faculty at six universities to develop curricula for courses common across the same disciplines at multiple universities in order to reduce the amount of time that any individual professor spends on creating what is essentially duplicate materials. The method proposed in this workshop is based on open source software development, where code is shared in online repositories, reviewed by peers, and contributed to the main project.
*June 2017*
**Department of Energy**
**Participant**
*Consent-Based Siting Public Meeting*
The Department of Energy is in the initial phase of developing a consent-based process for siting the facilities needed to store and dispose of the nation’s spent nuclear fuel and high-level radioactive waste. A consent-based approach to siting relies on understanding the views of the public, stakeholders, and governments at the local, state, and tribal levels. In this first phase, the Department is engaging with interested groups and individuals to learn about what elements are important to consider in designing an enduring approach to siting. This session is an opportunity for the public to share thoughts and perspectives through a facilitated discussion.
*July 2016*
**Global American Business Institute**
**Invited participant**
*Trilateral Nuclear Energy Dialogue: Korea, Japan, United States*
Convene a high-level private workshop among preeminent Korean, Japanese, and American experts in nuclear energy and nuclear policy issues, with the intention of fostering relationships, confidence building, and seeking potential areas for trilateral cooperation. In keeping with the overarching theme of previous discussions—the back-end fuel cycle—this meeting seeks to underscore the role of advanced nuclear energy and fuel cycle technologies. Although the obstacles impeding permanent solutions to spent fuel and radioactive waste are largely political, this dialogue aims to highlight the potential of cutting-edge technologies in addressing the policy, environmental, and public acceptance challenges facing management of the nuclear fuel cycle, in addition to opportunities for international collaboration in the research, development, demonstration, and deployment of such technologies.
*July 2016*
**Pacific Northwest National Laboratory**
**Invited participant**
*Next Generation Safeguards Initiative Summer Course*
This course, offered through the DOE/NNSA Next Generation Safeguards Initiative (NGSI), covers major international safeguards procedures currently in use in IAEA member nations. Daily lectures were supplemented with hands-on safeguards activities conducted by IAEA safeguards inspectors and researchers at PNNL. Participants included faculty, postdoctorate researchers, and graduate students.
*June 2016*
**Boise State University**
**Participant**
*Idaho's Role in Nuclear: Clean Energy Powered by the Next Generation*
Boise State University is proud to bring globally recognized leaders in nuclear energy to address the benefits and challenges associated with nuclear energy production and its role in supplying clean energy for a growing world. The summit will also include a panel discussion with John Kotek, Assistant Director of Nuclear Energy, U.S. Department of Energy; Dr. Mark Peters, Laboratory Director for the Idaho National Laboratory; Mark Rudin, Vice President for Research at Boise State University; Mike McGough, Chief Commercial Officer at NuScale Power, and Dr. Harold Blackman, Associate Vice President for Research and Economic Development at Boise State University. The panel will address questions about the benefits of and concerns around nuclear power.
*March 2016*
**Portland State University**
**Participant**
*National Science Foundation Grant Development Conference*
Key officials representing each NSF program directorate, administrative office, Office of General Counsel, and Office of the Inspector General will participate in this two-day conference. The conference is considered a must, particularly for new faculty, researchers, educators and administrators who want to gain insight into a wide range of important and timely issues at NSF, including: the state of current funding; the proposal and award process; and current and recently updated policies and procedures.
*February 2016*
**University of California-Berkeley**
**Invited participant**
*Proliferation Resistance and Physical Protection Working Group Workshop*
The PR&PP methodology was developed within the Generation IV International Forum (GIF) to provide a structured framework to assess the proliferation resistance and physical protection robustness of Gen IV nuclear energy systems, and to guide designers to further improve their systems. This workshop is intended to familiarize non-experts in this field with the broad aspects of the methodology and its applications. The PR&PP Working Group will present an overview of the methodology to an audience of students, academics, and members of the GIF community who wish to become more familiar with the PR&PP methodology. To illustrate the methodology, its application to a hypothetical nuclear energy system will be examined. Workshop participants will be divided into subgroups that will consider different proliferation and security threats, and will identify important design features and approaches that contribute to the system’s resilience to these threats. Following these subgroup sessions, workshop participants will reconvene to review insights from the subgroups. Finally, an open discussion will be held to obtain feedback from the participants on the GIF approach to PR&PP with the objective of refining the methodology and its presentation to the wider community of academics and prospective GIF users.
*November 2015*
**State of Idaho Board of Education, Boise, Idaho**
**Invited participant**
*Open educational resources development*
This workshop focused on the use of open source educational materials in order to produce an online textbook as a supplement to existing commercial textbooks. An online textbook allows flexibility for faculty to augment content without requiring multiple textbooks for a course. An online textbook allows the educational content of a course to be more closely aligned with the desired learning outcomes. Two online texts have been developed: Principles of Nuclear Engineering and Risk Assessment.
*October 2015*
**University of California-Berkeley, Department of Nuclear Engineering**
**Discussant**
*Advanced summer school of radioactive waste disposal with social-scientific literacy*
*Reflections on the Fukushima nuclear accident and beyond*
This advanced summer school was established in conjunction with the Department of Nuclear Engineering/Management, the University of Tokyo and the Department of Nuclear Engineering, University of California, Berkeley to provide Ph.D. students and early-career nuclear engineers with education in social sciences and engineering. The goal was to foster a next generation of engineers capable of understanding the public and societal needs, contributing to the societal decision making, and takingi a responsible role as engineering experts in society. The discussant leads student group activities by stimulating questions from students and corroborating with the chair to develop a summary of lectures.
*August 2011*
**University of California-Berkeley, Department of Nuclear Engineering**
**Invited participant**
*Minner fellows program*
The objective of this program was to develop a framework for making ethical judgments in engineering. Because engineering faculty and graduate students play a leadership role in the development of these technologies, it is essential that they become aware the ethical, legal and social ramifications of them. The course focused on context, or the embodiment of moral maturity and ethical expertise, in the same way that faculty and graduate students embody engineering and technical expertise.
*June 2011*
**Hawai’i Tokai International College**
**Project mentor**
*Advanced summer school of radioactive waste disposal with social-scientific literacy*
Special emphasis was placed on integrating nuclear science and engineering with social science. A series of lectures and student group discussions were conducted, followed by a student workshop in which projects were developed, under the theme of ‘nuclear engineers in society,’ including topics such as the safety of a high level waste repository and nuclear systems for non-nuclear weapons states. Project mentors provided guidance, direction, and oversight. The school ended with a series of project presentations and submittal of project reports.
*August 2010*
**University of California-Berkeley, Department of Nuclear Engineering**
**Student**
*Advanced summer school of radioactive waste disposal with social-scientific literacy*
In this summer school, The integration of nuclear science and engineering with social science was emphasized through a series of lectures, panel and group discussions. Students directed discussions based on the activities each day. The school culminated in a tour of the Waste Isolation Pilot Plant (WIPP).
*August 2009*
**University of California-Berkeley, Graduate Student Instructor Teaching & Resource Center**
**Participant**
*Summer Institute for Preparing Future Faculty*
This unique program is for Doctoral Candidates with an interest in an academic career. Many aspects of teaching are covered: course design, syllabus development, teaching and learning assessment, teaching and learning strategies, and the creation of a teaching portfolio. The program exposes candidates to faculty in several disciplines both within and outside the university; thus allowing for the dissemination of the full scope of teaching methods and skills, as well as broadening of perspectives with regards to the entire teaching profession.
*May 2005 – June 2005*
___
# Awards and fellowships
**University of Idaho**
**American Nuclear Society University of Idaho Student Section**
Samuel Glasstone Award for Public Service - Second Place
*2019*
**University of California-Berkeley, Department of Nuclear Engineering**
Nuclear Engineering Department Block Grant Fellowship
*2005*
Outstanding Graduate Student Instructor Award
*2003*
Katherina S. DeSharton Fellowship
*1999*
Hamilton Family Memorial Fellowship
*1999*
**United States Department of Energy, Office of Civilian Radioactive Waste Management**
Civilian Radioactive Waste Management Fellowship
*2000 – 2004*
**Nuclear Energy Institute**
National Academy for Nuclear Training Fellowship
*1999*
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# Professional societies and related activity
Faculty Advisor - American Nuclear Society, University of Idaho Student Section
Community Service - Idaho American Nuclear Society
Board of Directors - Idaho American Nuclear Society, 2018-19; 2020-21
Executive Committee Member - Fuel Cycle and Waste Management Division, American Nuclear Society, 2018-21
Executive Committee Member - Nonproliferation Policy Division, American Nuclear Society, 2019-22
Executive Committee Member - Student Sections Committee, American Nuclear Society, 2018-21
Tau Beta Pi Engineering Society
___