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)

Other versions:

(Verbatim name)

(Catalog Number)

DES

Invalid DOI was provided, please try again

(1)

(0)

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

Subscribe to email alerts for current Article's categories

This website uses cookies in order to improve your web experience. Read our Cookies Policy