Volkan Seker, Ph.D.

Affiliations: 
2007 Nuclear Engineering Purdue University, West Lafayette, IN, United States 
Area:
Nuclear Engineering
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"Volkan Seker"

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Thomas J. Downar grad student 2007 Purdue
 (Multiphysics methods development for high temperature gas reactor analysis.)
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Publications

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Seker V, Zhou H, Downar TJ. (2020) Development and Analysis of TREAT Neutronics Benchmarks Nuclear Technology. 206: 805-824
Xu Y, Seker V, Downar TJ. (2020) Quasi-Diffusion Method with 3-D Cross Sections for TREAT Core Analysis Nuclear Technology. 206: 825-838
Lee SN, Tak N, Lim H, et al. (2020) Benchmark calculations for verification of thermo-fluid analysis codes using simplified model of the OECD/NEA MHTGR-350 core design Annals of Nuclear Energy. 139: 107249
Seker V, Downar TJ. (2014) Validation of AGREE with HTTR control rod withdrawal tests Transactions of the American Nuclear Society. 110: 416-418
Tak NI, Kim MH, Lim HS, et al. (2013) Validation of numerical methods to calculate bypass flow in a prismatic gas-cooled reactor core Nuclear Engineering and Technology. 45: 745-752
Park HH, Saller T, Seker V, et al. (2013) Neutronics analysis of the high temperature engineering test reactor (HTTR) Transactions of the American Nuclear Society. 108: 799-802
Brown NR, Seker V, Revankar ST, et al. (2012) Transient simulation of an endothermic chemical process facility coupled to a high temperature reactor: Model development and validation Nuclear Engineering and Design. 248: 1-13
Brown NR, Seker V, Revankar ST, et al. (2012) An endothermic chemical process facility coupled to a high temperature reactor. Part I: Proposed accident scenarios within the chemical plant Nuclear Engineering and Design. 246: 256-265
Ward AM, Seker V, Xu Y, et al. (2012) A Newton-Krylov solution to the porous medium equations in the agree code International Conference On the Physics of Reactors 2012, Physor 2012: Advances in Reactor Physics. 3: 2241-2252
Ortensi J, Pope MA, Strydom G, et al. (2011) Prismatic core coupled transient benchmark Transactions of the American Nuclear Society. 104: 854-856
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