Feasibility study mixed oxide fuel tests in the impulse graphite reactor-Reference-Cited by-同舟云学术

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Feasibility study mixed oxide fuel tests in the impulse graphite reactor

Published:2022-09-25 Issue:3 Volume:6 Page:198-212
ISSN:2616-8537
Container-title:Eurasian Journal of Physics and Functional Materials
language:
Short-container-title:Eurasian j. phys. funct. mater.

Author:

Vityuk G. A.¹,Vityuk V. A.¹,Vurim A. D.¹,Skakov M. K.¹,Gradoboyev A. V.²

Affiliation:

1. National Nuclear Center of the Republic of Kazakhstan

2. Tomsk Polytechnic University

Publisher

L. N. Gumilyov Eurasian National University

Subject

Physics and Astronomy (miscellaneous),Condensed Matter Physics,Materials Science (miscellaneous),Nuclear and High Energy Physics,Radiation

Reference32 articles.

1. Y. Fukano, Journal of Nuclear Science and Technology 50 (2013) 950–965.

2. M. Sarotto et al., Possible working range of the MYRRHA core and basic neutronic parameters for safety analyses. Quality Assurance Document. UTFISSM-P9B2-004 Rev. 0 (ENEA, Centro Ricerche Saluggi, Italy, 2014) 32 p.

3. L. Rui et al., Annals of Nuclear Energy 79 (2015) 31–42.

4. I.V. Kurchatov et al., Soviet Atomic Energy 17 (1964) 1224–1235.

5. V.A. Vityuk et al., Atomic Energy 120 (2016) 323–327.

Cited by 2 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Conceptual View of the Nuclear Energy Program Implementation in the Republic of Kazakhstan;2024

2. Testing of a heterogeneous fuel rod in the research Impulse graphite reactor;Progress in Nuclear Energy;2023-10

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