GOKHAN YESILYURT
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About

Gokhan Yesilyurt
Nuclear Engineer, Ph.D.VITA
Gokhan Yesilyurt, son of Nuri and Hulya Yesilyurt, was born on April 16, 1976 in Kutahya, Turkey. He attended to Malatya Science High School for two years and graduated from Ataturk High School in 1993 in Kutahya. He continued his education at Hacettepe University, in Ankara and received his Bachelor of Science degree in Nuclear Engineering in 1999. He received his Master of Science degree in Nuclear Engineering from Texas A&M University in 2004. He got admitted by the University of Michigan for the doctorate program and received his Ph.D. degree from Nuclear Engineering and Radiological Sciences in 2009. He pursued his career as the post-doctoral research associate at the Oak Ridge National Laboratory from 2009 to 2011. He worked as an R&D Nuclear Engineer at the Argonne National Laboratory between 2011 and 2016. Then, he Joined X Energy, LLC in 2016 and currently working on Pebble Bed Advanced GasCooled Reactor mechanistic source term code development.
RESEARCH INTERESTS
An accomplished nuclear engineer specializing in nuclear reactor modelling and analysis; probabilistic and deterministic nuclear transport theory methods, development and applications of Monte Carlo and lattice physics burnup codes, fuel performance, mechanistic source term code development, thermal-hydraulics, nuclear data processing, fuel management and decay heat analysis, development of coupled nuclear-thermal-hydraulic applications for nuclear reactor analysis, computational fluid dynamics (CFD), turbulence models, high performance computing, development and administration of massively parallel clusters and a wide variety of computer programming and scripting languages.
BRIEF SUMMARY OF QUALIFICATIONS
• Excellent knowledge, understanding and expertise in Monte Carlo code development and applications. Experience with the industry standard radiation transport codes such as MCNP5 and KENO VI. • Experience with three-dimensional fuel performance codes AMP, BISON, FRAPCON and FRAPTRAN. • Excellent experience in mechanistic source term code development for qualification of Pebble Bed high temperature gas cooled reactors (HTGRs). • Experience with SCALE sequences such as SCALE/TRITON/NEWT and SCALE/TRITON/T-DEPL. • Solid background and experience in nuclear fuel management. Performed the Massachusetts Institute of Technology research reactor fuel management studies with MCODEFM for low enriched uranium conversion. • Experience with fast reactor fuel cycle analysis code system DIF3D/REBUS-3. Performed a scoping design study for Multi-Purpose Fast Research Reactor MBIR, using these tools. • Demonstrated implementation skills in deterministic nuclear transport theory methods. Experience with advanced lattice physics burnup code CPM3 and three-dimensional discrete ordinates (SN) transport code DENOVO. • Experience with 3-D reactor core simulator PARCS. • Solid background and expertise in nuclear data processing code NJOY and development of practical methods, including on-the-fly Doppler broadening during the random walk of the neutrons for the Monte Carlo codes. • Experience in development of coupled nuclear-thermal-hydraulic applications, utilizing MCNP5, RELAP-3D/ATHENA and ORIGEN2 for the analysis of VHTRs. • Experience with commercial CFD codes such as CFX and FLUENT. • Excellent knowledge and expertise in computer programming, Unix/Linux administration and clustering technologies to increase the scalability of mission-critical applications. Demonstrated implementation skills and proficiency in computer programming languages C&C++, F77, F90, MPI, Socket Programming, Perl, Awk, Bash, Php, Mysql, Multi-threading, Networking and industry standard programs such as Matlab, Oracle, Sybase, and other similar programs.