Nitride Fuel for a Prospective BN-1200 Type Fast Sodium Reactor

Nitride Fuel for a Prospective BN-1200 Type Fast Sodium Reactor

The developers of fast sodium reactors are studying nitride fuel for use soon after oxide fuel. Together with a significant increase in the total BR, dense nitride fuel also permits improving a characteristic that is important for reactor safety – significantly decreasing the reactivity excess on bu...

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Veröffentlicht in:Atomic energy (New York, N.Y.) N.Y.), 2013-09, Vol.114 (5), p.331-336
Hauptverfasser: Eliseev, V. A., Zaboudko, L. M., Malysheva, I. V., Matveev, V. I.
Format: Artikel
Sprache:eng
Schlagworte:
Hadrons
Heavy Ions
Helium
Nitrogen
Nuclear Chemistry
Nuclear Energy
Nuclear engineering
Nuclear fuels
Nuclear Physics
Nuclear reactors
Physics
Physics and Astronomy
Reactors
Sodium
Studies
Uranium
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Beschreibung
Zusammenfassung:The developers of fast sodium reactors are studying nitride fuel for use soon after oxide fuel. Together with a significant increase in the total BR, dense nitride fuel also permits improving a characteristic that is important for reactor safety – significantly decreasing the reactivity excess on burnup. The results of physical calculations of a BN-1200 reactor core, using fuel elements with gas or sodium sublayer on nitride fuel, are presented.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-013-9720-0