Extension of lifespan of graphite in fuel blocks of high-temperature gas-cooled reactors as the resource for ensuring design values of nuclear fuel burn-up *

Olga I. Bulakh; Oleg K. Kostylev; Vladimir N. Nesterov; Eldar K. Cherdizov

doi:10.3897/nucet.5.48391

Research Article

Nuclear Energy and Technology 5(4): 289-295
https://doi.org/10.3897/nucet.5.48391 (10 Dec 2019)

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A E Kruglikov, Y N Volkov, M N Zizin, V F Boyarinov, V A Nevinitsa, P A Fomichenko (2020)
Computational analysis of experiments to determine the kinetic parameters at the ASTRA HTGR type critical facility. Journal of Physics: Conference Series 1689: 012025.

DOI: 10.1088/1742-6596/1689/1/012025

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