Influence of the Graphite’s Lifespan on the Design Value of Fuel Burnup in High Temperature Gas-Cooled Reactors

Denis F. Baybakov; Aleksey V. Golovatsky; Artem G. Naymushin; Vladimir N. Nesterov; Savva N. Savanyuk; Igor V. Shamanin

doi:10.4028/www.scientific.net/AMR.1084.313

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Determining Reactor Graphite Lifespan from Thermal Properties Degradation
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Facilities for Neutron Capture Therapy at IRT MEPhI Nuclear Reactor
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Feasibility Study of Using New Fuel Composition in IRT-T Research Reactor
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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
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Preparation of ¹⁸⁸ W from Unenriched Targets in Middle Flux Nuclear Reactors
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Reactor Model for Plasma Utilization of Dispersed Water-Organic Compositions Based on a Closed Nuclear Fuel Cycle Inflammable Wastes
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Research of Possibility of Sludge Complex Recycling in Low Radioactive LRW Storage Pools
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Technology for Silicon NTD Using Pool-Type Research Reactors
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HomeAdvanced Materials ResearchAdvanced Materials Research Vol. 1084Influence of the Graphite’s Lifespan on the Design...

Influence of the Graphite’s Lifespan on the Design Value of Fuel Burnup in High Temperature Gas-Cooled Reactors

Abstract:

This paper describes a method of determining the correlation of the exhausted graphite fuel blocks’ lifespan in high temperature gas-cooled reactors with the fuel burnup. The axial distribution of the local values of the exhausted lifespan of graphite fuel blocks was obtained. It is shown that for ensuring the compliance of the design value of the fuel burnup with graphite fuel blocks operability, it is necessary to reduce the average mixed temperature of the helium coolant leaving the reactor core and as well as reduce the time between nuclear fuel recharges.

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Periodical:

Advanced Materials Research (Volume 1084)

Pages:

313-316

DOI:

https://doi.org/10.4028/www.scientific.net/AMR.1084.313

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Online since:

January 2015

Authors:

Denis F. Baybakov, Aleksey V. Golovatsky, Artem G. Naymushin, Vladimir N. Nesterov, Savva N. Savanyuk, Igor V. Shamanin

Keywords:

Graphite Lifespan, Graphite Moderator, HTRG, Nuclear Fuel Burn-Up

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