Determining Reactor Graphite Lifespan from Thermal Properties Degradation

Denis Baybakov; Artem Naymushin; Vladimir Nesterov; Sevastyan Savanuk; Igor Shamanin

doi:10.4028/www.scientific.net/AMR.1084.294

Paper Titles

Advantages of Thorium Nuclear Fuel for Thermal-Neutron Reactors
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Angular Distributions of EUV Generated by Electrons with 5.7 MeV Energy in a Multilayer Mo/Si Structure
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Conceptual Approach to Handling Irradiated Nuclear Fuel in Storage Systems
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Degradation of Beryllium Reflector Properties on the IRT-T Reactor
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Determining Reactor Graphite Lifespan from Thermal Properties Degradation
p.294

Facilities for Neutron Capture Therapy at IRT MEPhI Nuclear Reactor
p.298

Feasibility Study of Using New Fuel Composition in IRT-T Research Reactor
p.306

Formation of the Irradiation Zone for Neutron Transmutation Doping Using the Pool-Type Research Reactor
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Influence of the Graphite’s Lifespan on the Design Value of Fuel Burnup in High Temperature Gas-Cooled Reactors
p.313

HomeAdvanced Materials ResearchAdvanced Materials Research Vol. 1084Determining Reactor Graphite Lifespan from Thermal...

Determining Reactor Graphite Lifespan from Thermal Properties Degradation

Abstract:

This work assesses real graphite lifespan distribution of pressurized-tube reactors (RBMK) with graphite moderator. The changes in heat exchange and heat transfer conditions were taken into consideration, which changes are induced by the thermal properties’ degradation and the changes in the form of structural elements. Besides, some features associated with the differences in the neutron flux spectrum and differences in characteristics of gamma radiation field in the fuel and in the channels of control and protection system (CPS) were all taken into account.

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Periodical:

Advanced Materials Research (Volume 1084)

Pages:

294-297

DOI:

https://doi.org/10.4028/www.scientific.net/AMR.1084.294

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Online since:

January 2015

Authors:

Denis Baybakov, Artem Naymushin*, Vladimir Nesterov, Sevastyan Savanuk, Igor Shamanin

Keywords:

Control, Graphite Lifespan, Pressurized-Tube Reactor, Protection System Cells, RBMK-1000

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* - Corresponding Author

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