Researcher

Gerhard Strydom

Specialist

Research Areas:

Biography:

Gerhard Strydom is a Very High Temperature Reactor core dynamics specialist at Idaho National Laboratory. In this capacity, his work primarily focuses on High Temperature Reactor physics, transient analysis, and uncertainty and sensitivities studies in couple code analysis.

Strydom has more than seven years of experience as a nuclear engineer analyst in South Africa. He holds an MSC in nuclear reactor physics from Northwest University in South Africa and is a member of the American Nuclear Society. Outside of work he enjoys hiking, motorcycling, biking and travel.

Education:

M.S., Reactor Science - North West University, South Africa

Postgraduate Diploma, Reactor Engineering - University of Witwatersrand, South Africa

Postgraduate Diploma, Project Management - University of Pretoria, South Africa

B.S., Physics - Universitry of the Orange Free State, Bloemfontein, South Africa

Publications:

P. Rouxelin, G. Strydom, et al., “The IAEA CRP on HTGR Uncertainties: Sensitivity Study of PHISICS/RELAP5-3D MHTGR-350 Core Calculations using Various SCALE/NEWT Cross-Section Sets for Ex. II-1a”, Nuclear Engineering and Design, Vol. 329, pp 156–166 (2018).

F. Bostelmann, G. Strydom, et al., “Nuclear data uncertainty and sensitivity analysis of the VHTRC benchmark using XSUSA and SCALE”, Annals of Nuclear Energy 110, pp. 317-329 (2017).

D. Petti, et al., “A Summary of the Department of Energy’s Advanced Demonstration and Test Reactor Options Study”, Nuclear Technology, Vol. 199, Issue 2 (2017).

F. Bostelmann, G. Strydom, et al., “The IAEA coordinated research programme on HTGR uncertainty analysis: Phase I status and Ex. I-1 prismatic reference results”, Nuclear Engineering and Design, Vol. 306, pp. 77-88 (2016).

G. Strydom, et al., “Comparison of the PHISICS/RELAP5-3D ring and block models results for Phase I of the OECD/NEA MHTTGR-350 benchmark”, Nuclear Technology 193(1), pp 15-35 (2016).

G. Strydom, “Uncertainty and Sensitivity Analysis of a Pebble Bed HTGR Loss of Cooling Event”, Science and Technology of Nuclear Installation 2013 (2013).

G. Strydom, “Preliminary reactor physics assessment of the HTR module with 14% enriched UCO fuel”, Nuclear Engineering and Design 256, pp 304-321 (2012).

B. Boer, et al., “Validation of the DALTON-THERMIX code system with transient analyses of the HTR-10 and application to the PBMR”, Nuclear Technology 170 (2), pp 306-321 (2010).

G. Strydom, “Xenon-induced spatial power oscillations in the 400 MW PBMR reactor”, Nuclear Engineering and Design 238 (11), pp 2960–2975 (2008).

F. Reitsma, G. Strydom et al., “The PBMR steady-state and coupled kinetics core thermal-hydraulics benchmark test problems”, Nuclear Engineering and Design 236 (5), pp 657–668 (2006).

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