NICHOLAS PATRICK LUCIANO

phone: (865) 241-3912 Oak Ridge National Laboratory fax: (865) 574-0382 PO Box 2008 MS6165 email: [email protected] Oak Ridge TN 37831-6165 web: https://ornl.gov/staff-profile/nicholas-p-luciano

CURRENT RESEARCH Calculation of spent fuel isotopics of US and international fuel designs for global material security. Benchmarking nuclear core transport and depletion codes against operational data from a Russian- designed VVER light water reactors. Modeling of thorium fuel cycles for safeguards technology needs assessments. High fidelity computational modeling of plutonium production reactors for proliferation detection and material provenance assessments. Modeling of fast reactor fuel depletion of mixed- oxide fuel for plutonium disposition. Nuclear forensic modeling.

RESEARCH INTERESTS Computational modeling of spent nuclear fuel, reactor physics, and nuclear fuel cycles, including: modeling and simulation tools development; reactor core physics design and analysis, fuel cycle eval- uations; characterization of spent fuel isotopic inventories; development of reactor analysis methods; fast-spectrum, small modular, and molten salt reactor designs; MOX fuel for plutonium disposition; criticality safety and spent fuel storage; inverse problems; uncertainty quantification and sensitivity analysis; accelerator applications; nuclear policy issues.

EDUCATION • University of Ph.D. Nuclear Engineering – Dissertation Advisor: Professor G. Ivan Maldonado – Dissertation Title: Sensitivity of VVER-1000 Spent Fuel Pin Nuclide Inventory to Oper- ational Parameters • M.S. Nuclear Engineering – Master’s Thesis Advisor: Erik B. Iverson – Thesis Title: A High-Energy Neutron Flux Spectra Measurement Method for the Spallation Neutron Source • Institute of Technology B.S. Physics.

EXPERIENCE R&D Staff Oak Ridge National Laboratory Jul 2016 - present Oak Ridge, TN R&D Associate in the Nuclear Security Modeling group in the Nuclear Nonproliferation Division. Primary role is to investigate the security implications of spent nuclear fuel, nuclear reactors, fuel cycles by using modeling & simulation tools. Work has focused on isotopic content of spent nuclear fuel for security applications.

Research Associate University of Tennessee Oct 2010 - Jul 2016 Knoxville, TN Research was focused on improved accuracy of isotopic content of spent fuel using diffusion nodal core simulations. Previous work includes neutron flux spectra measurements using HPGe gamma-ray spectrometry, fuel pin modeling for neutron and gamma-ray monitoring and inspection, calculation of neutronic figures of merit for material attractiveness. Additional work includes development and maintenance of the NESTLE nodal core simulator software, high fidelity Monte Carlo simulation of VVER-1000 core for detailed spent fuel isotopics, and modeling of control rod depletion for small modular reactors. Engineer III Sigma Science June 2014 - Jul 2016 Los Alamos, NM Responsible for analyses in support of the the fissile material disposition program.

Staff Engineer Primm Consulting Oct 2012 - July 2014 Knoxville, TN Responsible for analyses and reports for plutonium disposition monitoring and inspection regime.

Staff Engineer DQS GAMA Network Solutions Oct 2012 - June 2014 Knoxville, TN Responsible for requested analyses related to material attractiveness program.

Summer Intern Babcock & Wilcox Company May 2012 - Aug 2012 Lynchburg, VA Worked onsite at B&W Generation mPower, performing verification of fuel lattice and core neu- tronics using SCALE 6.1 software. Technical Staff Oak Ridge National Laboratory Mar 2006 - Jul 2010 Oak Ridge, TN Control Room Shift Supervisor at the Spallation Neutron Source (SNS) where responsibilities in- cluded overseeing shift personnel, operation of the proton accelerator. Worked independently to design improvements for the SNS ion source and controls systems. Received a Supplemental Perfor- mance Award for Safety Vigilance in SNS Operations

Technical Staff Brookhaven National Laboratory Apr 2001 - Jan 2006 Upton, NY Physics associate at the Brookhaven National Laboratory in Upton, NY. Responsible for particle beam operation, access to radiation areas, and adherence to radiation safety procedures as part of a rotating shift team. Acted as a liaison between experimenters and staff, assisted physicists with studies, and worked independently to develop a novel design for ion beam instrumentation at the Relativistic Heavy Ion Collider.

Student Assistant Neely Nuclear Research Center 1997-2000 Georgia Institute of Technology, Atlanta, GA Assisted Senior Reactor Operator in maintenance of radiation control zone and hot cell.

QUALIFICATIONS Licensed professional nuclear engineer. Demonstrated ability to work independently or with a team of scientists and engineers. Experience working with large datasets in a parallel computing en- vironment. Demonstrated commitment to safe laboratory and work practices. Excellent verbal, presentation, and writing skills. Active DOE Q Clearance with SCI compartments. Experience in a classified work environment with derivative classifier qualification.

SKILLS Experience building and analyzing fuel assemblies and whole-core reactor computer models of pluto- nium production reactors, PWRs, BWRs, VVERs, and sodium cooled fast reactors. Extensive expe- rience with nuclear reactor analysis codes including NESTLE, SCALE (KENO, TRITON, NEWT, etc.), MCNP, VESTA, SERPENT, and other lattice physics code systems, reactor core physics anal- ysis codes, and radiation transport codes. Experience with DOE CASL tools including VERA and MPACT. Limited experience with Studsvik codes CASMO and SIMULATE, and the cross section generation code NJOY. Experience with computer operating systems including Linux, Apple OS X, Windows. Extensive experience with programming languages including Modern Fortran, Python, C/C++, Matlab. Experience with software tools such as Eclipse, Git, Doxygen, CMake, LATEX. Proficiency in MS Word and Excel. AWARDS AND HONORS • Department of Energy Certificate of Appreciation, NMIP, 2019 • Innovations in Fuel Cycle Research Award, U.S. Department of Energy, 2016 • Student at the MeV School in Reactor Physics, Argonne National Lab, 2011. • Nuclear Engineering Student Delegate to Washington, D. C., 2009. • Baker Scholar at the University of Tennessee Howard Baker Jr. Center for Public Policy, 2009. • Winner - ANS Student Design Competition Internal Instrumentation for a Spent Nuclear Fuel Dry Storage Cask, 2008. • ORNL Supplemental Performance Award for Safety Vigilance in SNS Operations, 2008.

PUBLICATIONS • C. Gentry, V. Seker, B. Ade, A. Conant, N. P. Luciano, K.S. Kim, B. Collins, T. Downar. Development and Performance Simulations of the MPACT-AGREE Code Coupling Interface for MAGNOX Reactors. In proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Raleigh, NC, Oct 2021. Accepted • N. P. Luciano, B. Grogan, A. Ulses. Rapid Calculation of Spent-Fuel Gamma-Ray Dose Rates Using Response Functions for Self-Protection Estimates. In proceedings of INMM & ESARDA Joint Annual Meeting, Vienna Austria, Aug 2021. In Preparation • E.C. Uribe, S.M. Gilbert, L.G. Worrall, N. P. Luciano, R.L. Reed, N.A. McGirl, J.J. Powers. Accountable Nuclear Material Production from Fissile Isotope Precursors in Advanced Fuel Cycles: The Case of Protactinium-233. In proceedings of INMM & ESARDA Joint Annual Meeting, Vienna Austria, Aug 2021. In Preparation • P. Suk, O. Chvala, G.I. Maldonado, N. P. Luciano. Evaluation of End of Cycle Plutonium Isotopic Content in a VVER-1000 Reactor using a 3D Full-Core Simulator. Nuclear Engineer- ing and Design (2021). Accepted • B. Grogan and N. P. Luciano. Commercial Nuclear Fuel Types Produced in the United States for Domestic Use: 1957-2016. Oak Ridge National Laboratory Technical Report ORNL/SPR- 2021/1789 (2021). • L.G. Evans, V. Henzl, A. Swift, N. P. Luciano, et al. Safeguards Technology for Thorium Fuel Cycles. Oak Ridge National Laboratory Technical Report (2021). • N. P. Luciano, B. Ade, K.S. Kim, A. Conant. Verification of MPACT using Magnox Reactor Neutronics Progression Problems. In proceedings of The Physics of Reactors - Physor 2020, Cambridge, UK, Apr 2020. • K.S. Kim, B. Ade, N. P. Luciano. Development and Verification of the 69-Group Library for Magnox Reactor Analysis. In proceedings of The Physics of Reactors - Physor 2020, Cambridge, UK, Apr 2020. • B. Ade, N. P. Luciano, C. Gentry, S. Stimpson, B. Collins, R. Mills. Development of MPACT for Full-Core Simulations of Magnox Gas-Cooled Reactors. In proceedings of The Physics of Reactors - Physor 2020, Cambridge, UK, Apr 2020. • O. Novak, O. Chvala, N. P. Luciano, G. Ivan Maldonado. VVER 1000 Khmelnitskiy bench- mark analysis calculated by Serpent2. Annals of Nuclear Energy, 110, pp 948-957 (2017). DOI: 10.1016/j.anucene.2017.08.011 • O. Novak, L. Sklenka, O. Huml, J. Frybort, O. Chvala, N. P. Luciano, G.I. Maldonado. Benchmark evaluation of zero-power critical parameters for the Temelin VVER nuclear reactor using SERPENT & NESTLE and MCNP. Nuclear Engineering and Design, 253, (2019). DOI: 10.1016/j.nucengdes.2019.110243 • C.F. Weber, M.Francis, A.D. Nicholson, S. Stewart, L. Worrall, K.J. Dayman, N. P. Luciano, B. Ade, M. Adams. Transformative Data Analytics Capabilities for Nuclear Forensics and Safeguards. In proceedings of The 60th Annual Meeting of the Institute of Nuclear Materials Management, Palm Desert, CA, Jul 2019. • N. P. Luciano, G.I. Maldonado. Two-dimensional hexagonal geometry discontinuity factors at the core periphery. Annals of Nuclear Energy pp 49-52 107 (2017). DOI: 10.1016/j.anucene.2016.11.029 • L.G. Worrall, E.D. Collins, J. Cooley, S. Croft, B.K. Davies, A. Favalli, B.R. Grogan, V. Henzl, K. Hogue, A.M. Krichinsky, N. P. Luciano, C. Lloyd, A. Swift, A. Worrall, J. Yang. Safeguards Challenges and Safeguards Technology Needs Assessment for Leading Thorium Fuel Cycles. In proceedings of Symposium on International Safeguards: Building Future Safeguards Capabilities, Vienna, Austria, Nov 2018. • N. P. Luciano, V.J. Jodoin. Establishing and Testing WSB, a Code to Compute the Cloud Rise and Fallout Due to Water Surface Bursts. Oak Ridge National Laboratory Technical Report ORNL/SP-2017/174 (2017). • N. P. Luciano, K.E. Ottinger, G.I. Maldonado. Verification of the Pin Power Reconstruc- tion Method in NESTLE. In proceedings of Top Fuel 2016 Light Water Reactor (LWR) Fuel Performance Meeting, Boise, ID, Sep 2016. • N. P. Luciano, G.I. Maldonado. Modeling and Simulation of and Operational VVER-1000 Benchmark with NESTLE. In proceedings of ICAPP 2016) International Congress on Ad- vances in Nuclear Power Plants, San Francisco, CA, Apr 2016. • N. P. Luciano, et al.. The NESTLE 3D Nodal Core Simulator: Modern Reactor Models. In proceedings of ANS MC2015 Joint International Conference on Mathematics and Computa- tion, Nashville, TN, Apr 2015. • N. P. Luciano, P. E. Collins, G.I. Maldonado, I. Gauld. Modeling and Simulation of a VVER- 1000 Benchmark with High Fidelity Monte Carlo Codes and Realistic Whole Core Operational Conditions. Oak Ridge National Laboratory Technical Report ORNL/SPR-2015/265 (2015). • K.E. Ottinger, P. E. Collins, N. P. Luciano, G.I. Maldonado. SMR Fuel Cycle Optimization and Control Rod Depletion Using NESTLE and LWROPT. In proceedings of ANFM 2015 Advances in Nuclear Fuel Management V, Hilton Head Island, SC, Apr 2015. • P.E. Collins, N. P. Luciano, G.I. Maldonado. Modernization and Expansion of Isotopic Depletion Capabilities within the NESTLE 3D Nodal Simulator. Transactions of the , 111, 1230 (2014). • P.E. Collins, N. P. Luciano, G.I. Maldonado. Parametric Study to Capture the Skin Effect in PWR Control Rod Depletion. Transactions of the American Nuclear Society, 109, 1327 (2013). • N. P. Luciano, P. Eric Collins, G. Ivan Maldonado. 3D Monte Carlo-Based Depletion of Control Rods for a Small PWR Core. Transactions of the American Nuclear Society, 109, 1325 (2013). • N. P. Luciano, J.E. Shamblin, G.I. Maldonado. Fast Reactor 3D Core and Burnup Analysis Using VESTA. In proceedings of PHYSOR 2012: Advances in Reactor Physics. Knoxville, TN, Apr 2012. • N. P. Luciano, E.B. Iverson. Neutron Flux and High Energy Flux Spectra Measurements Using Foil Activation at the SNS. In proceedings of Tenth International Topical Meeting on Nuclear Applications of Accelerators (AccApp ’11). Knoxville, TN, Apr 2011. • N. P. Luciano, H.Hernandez. Internal Instrumentation for a Spent Nuclear Fuel Dry Storage Cask. Transactions of the American Nuclear Society, 99 107 (2008). • R. F. Welton, M. P. Stockli, S. N. Murray, T. R. Pennisi, B. Han, Y. Kang, R. H. Gould- ing, D. W. Crisp, D. O. Sparks, N. P. Luciano, J. R. Carmichael, J. Carr. H(-) ion source developments at the SNS. Review of Scientific Instruments. 79, 02C721 (2008). DOI: 10.1063/1.2816937. • B. X. Han, R. F. Welton, M. P. Stockli, N. P. Luciano, J. R. Carmichael, J. Carr. Evaluation and utilization of beam simulation codes for the SNS ion source and low energy beam transport development. Review of Scientific Instruments. 79, 02B904 (2008). DOI: 10.1063/1.2819321. • R. F. Welton, M. P. Stockli, S. N. Murray, T. R. Pennisi, B. Han, Y. Kang, R. H. Goulding, D. W. Crisp, N. P. Luciano, J. R. Carmichael. In the Proceedings of Particle Accelerator Conference (PAC 07), Albuquerque, New Mexico, pp 658. (2007). DOI: 10.1109/PAC.2007.4439908 • N. P. Luciano, A. Nass, Y. Makdisi, P. Thieberger, D. Trbojevic, A. Zelenski. Luminescence Beam Profile Monitor for the RHIC Polarized Hydrogen Jet Polarimeter. Proceedings of 2005 Particle Accelerator Conference, Knoxville, Tennessee (2005) DOI: 10.1109/PAC.2005.1591797

EDUCATION INSTRUCTION • Guest Lecturer: – Nuclear Reactor Theory – Numerical Methods and Fortran – Reactor Theory and Design

CONFERENCES AND WORKSHOPS • Webmaster, M&C 2020 - Raleigh, NC • Registration Coordinator, IHLRWM 2019 - Knoxville, TN • Organizer/Lecturer: NESTLE Workshop, M&C 2015 - Nashville, TN • Organizer/Lecturer: NESTLE Workshop, PHYSOR 2014 - Kyoto, Japan • Organizing Committee, Student Coordinator: AccApp’11 - Knoxville, TN

PROFESSIONAL ASSOCIATIONS AND MEMBERSHIPS • Secretary, Oak Ridge / Knoxville American Nuclear Society • Member, Alpha Nu Sigma Nuclear Engineering • Member, Institute of Nuclear Materials Management • Nuclear Engineering Student Delegation, 2009

PROFESSIONAL PROFILES • ResearchGate: https://www.researchgate.net/profile/Nicholas Luciano • LinkedIn: https://www.linkedin.com/in/nluciano • Google Scholar: http://tinyurl.com/nick-luciano

OUTREACH ACTIVITIES • STEM Midway for ScoutFest 2019 sponsored by American Nuclear Society • Nuclear Science Week sponsored by the American Nuclear Society • Science Club Science Expo sponsored by the American Nuclear Society • Tennessee Science Bowl - Volunteer • Science Club Science Night sponsored by American Nuclear Society