Research Areas and Descriptors

General experience and professional interests include development of advanced numerical methods and algorithms for fuel depletion and thermal hydraulic coupled Monte Carlo codes. In addition, a special interest is to implement the developed methodologies in analysis of advanced reactor systems. Since, advanced systems usually aim to maximize a certain performance (e.g. fuel utilization), design optimization techniques are needed and are part of my research as well.

Education

  • B.Sc., Nuclear Engineering, Ben-Gurion University of the Negev, 2008
  • M.Sc., Nuclear Engineering, Ben-Gurion University of the Negev, 2010
  • Ph.D., Nuclear Engineering, Ben-Gurion University of the Negev, 2013

Background

Dr. Kotyar began at Georgia Tech in August 2016. Prior Dr. Kotlyar was a research associate in the Engineering Design Centre at the University of Cambridge, UK. He received his B.Sc. in Engineering in 2008 and PhD in Nuclear Engineering in 2013 from Ben-Gurion University. In 2014, he was elected a Research Fellow at Jesus College, where he contributed to undergraduate teaching and other educational activities.

At the University of Cambridge, his research is focused on the design of inherently safe light water reactors, more specifically, on the investigation of thorium-based fuel cycles for efficient plutonium incineration.

Research

My research is focused on the engineering of advanced nuclear power systems with their corresponding fuel cycles, and developing the required reactor physics tools to model them.

The unique characteristics of different advanced reactor systems have led to the conclusion that conventional techniques commonly used to model LWRs may not be applicable. These innovative nuclear systems require new tools that will be capable of accurate modelling. A primary research focus of mine is to develop tools to model ‘universal’ reactors while improving the reliability and efficiency of current codes. This part of my research deals with generalised method for Monte Carlo (MC) particle transport that could be applied to reactor physics codes. In addition, my research interests include development of numerical methods and algorithms for coupled Monte Carlo, fuel depletion and thermal hydraulic codes. Improving the reliability of existing deterministic methods (e.g. nodal diffusion codes) is also part of my portfolio.

Additional part of my research focuses on prolonging energy resources and minimizing nuclear waste worldwide by designing efficient fuel cycles. In this area, a part of my research is dedicated to studying Thorium based fuel cycles. Such a fuel cycle can be readily deployed in the current LWR technology. Thorium fuel cycle be applied to achieve a specific goal, such as better resource utilization or smaller repository sizing. Additional aspect of my research focuses on improving the performance and safety of the existing LWR reactor fleet by adopting new fuel/cladding types. I have studied various designs, such as: self-sustainable thorium-uranium water reactors, reduced moderation boiling water reactors, fluoride-cooled high-temperature reactors and fast reactors.

The area of additional interest is the application of optimisation methods to maximize the performance of various nuclear systems.

 

Selected Honors and Awards

  • ICONE23 Best Student Paper competition-Europe-competition, International conference on Nuclear Engineering, Makuhari Messe, Chiba, Japan (2015)
  • Best paper award, American Nuclear Society 2013 Student Conference, April 4-6, 2013, Boston, USA. (2013)
  • The Avner Einav Best Student Paper Award, 26th Conference of the Nuclear Societies in Israel, Dead Sea, Israel. (2012)

Representative Publications

  • L.W.G. Morgan, D. Kotlyar, 2015. “Weighted-Delta-Tracking for Monte Carlo Particle Transport,” Annals of Nuclear Energy, 85, 1184-1188.
  • D. Kotlyar, G.T.P Parks, E. Shwageraus, 2017. “Thorium-based Plutonium Incineration in the I2S-LWR,” Annals of Nuclear Energy, 100, 68-75.
  • D. Kotlyar, E. Shwageraus, 2016. “Stochastic Semi-Implicit Substep Method for Coupled Depletion Monte-Carlo Codes,” Annals of Nuclear Energy, 92, 52-60.
  • Y. Bilodid, D. Kotlyar, E. Shwageraus , E. Fridman, S. Kliem,  2016. “Hybrid microscopic depletion model in nodal code DYN3D,” Annals of Nuclear Energy, 92, 397-406.
  • B.A. Lindley, D. Kotlyar, G.T. Parks, J.N. Lillington, B. Petrovic, 2016. “Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes,” EPJ Nuclear Sci. Technol. 2, 14.
  • D. Kotlyar, E. Shwageraus, 2016. “Sub-step Methodology for Coupled Monte Carlo Depletion and Thermal Hydraulic Codes,” Annals of Nuclear Energy, 96, 61-75.
  • D. Kotlyar, G.T.P Parks, 2016. “Enhancing plutonium incineration in the thorium-based I2S-LWR design with simulated annealing loading pattern optimization,” Annals of Nuclear Energy, 96, 401-411.
  • D. Kotlyar, G.T.P Parks, E. Shwageraus, 2017. “Screening the design space for optimized plutonium incineration performance in the thorium-based I2S-LWR,” Annals of Nuclear Energy, 101, 237-249.
  • D. Kotlyar, B.A. Lindley, H. Mohamed, 2017. “Improving fuel utilization in SmAHTR with spectral shift control design: proof of concept,” Annals of Nuclear Energy, Proofed.
  • D. Kotlyar, M. Aufiero, E. Shwageraus, M. Fratoni, 2017. “A perturbation-based susbtep method for coupled depletion Monte-Carlo codes,” Annals of Nuclear Energy, 102, 236-244.