Investigative study of the radiation damage on fuel clad of miniature neutron source reactor using computational tools von Alhassan, S, Beliavskii, S V, Nesterov, V N

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Core-Optimization of Ritm-200 Reactor Fuel Considering Thorium Fuel Cycle von Alhassan, S., Beliavskii, S. V., Nesterov, V. N.

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Effect of fuel nuclide composition on the fuel lifetime of reactor KLT-40S von Beliavskii, Sergei V., Nesterov, Vladimir N., Laas, Roman A., Godovikh, Alexei V., Bulakh, Olga I.

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Effect of changing the outer fuel element diameter on thermophysical parameters of KLT-40S reactor unit von Beliavskii, S., Alhassan, S., Danilenko, V., Karvan, R., Nesterov, V.

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Fuel lifetime extension for the KLT-40S small modular reactor by means of thorium-uranium fuel cycle von Beliavskii, S., Balachkov, M., Danilenko, V., Nesterov, V.

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Effect of fuel nuclide composition on the fuel lifetime of the RITM-200 reactor unit von Beliavskii, S., Anikin, N., Alhassan, S., Kudeev, S., Nesterov, V.

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Evaluation of neutronic parameters for RITM-200 reactor unit considering (238U+235U)O2, (232Th+235U)O2 and (232Th+233U)O2 dispersed fuel using MCU-PTR von Alhassan, Samiru, Beliavskii, Sergey V, Nesterov, Vladimir N

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Evaluation of neutronic parameters for RITM-200 reactor unit considering (238U+235U)O2, (232Th+235U)O2 and (232Th+233U)O2 dispersed fuel using MCU-PTR von Alhassan, Samiru, Beliavskii, Sergey V, Nesterov, Vladimir N

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