Determination of the Parameters for Fuel Assembly Tests in a Pulsed Graphite Reactor

Determination of the Parameters for Fuel Assembly Tests in a Pulsed Graphite Reactor

This article is devoted to the development and testing of a new approach to the determination and prediction of the power parameters of tests of model fuel assemblies in the IGR reactor. A method based on the establishment of a relation between the thermophysical and power parameters of fuel assembl...

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Veröffentlicht in:Atomic energy (New York, N.Y.) N.Y.), 2016-09, Vol.120 (5), p.323-327
Hauptverfasser: Vityuk, V. A., Vurim, A. D., Kotov, V. M., Pakhnits, A. V.
Format: Artikel
Sprache:eng
Schlagworte:
Analysis
Assembly
Atomic energy
Corrosion
Energy
Experiments
Fuels
Graphite
Hadrons
Heavy Ions
Mathematical models
Melting
Nuclear Chemistry
Nuclear Energy
Nuclear fuels
Nuclear Physics
Nuclear reactors
Parameters
Physics
Physics and Astronomy
Plutonium
R&D
Reactors
Research & development
Sodium
Startups
Studies
Uranium
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Beschreibung
Zusammenfassung:This article is devoted to the development and testing of a new approach to the determination and prediction of the power parameters of tests of model fuel assemblies in the IGR reactor. A method based on the establishment of a relation between the thermophysical and power parameters of fuel assemblies is proposed. The results of experiments performed as part of the preparation of the fuel assemblies for the tests are presented. The power release in fuel assemblies and a relation between the power parameters of IGR and fuel assemblies at different levels of power release in the reactor are determined. The results obtained are used to determine the IGR operating regime in tests with melting of the fuel assemblies.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-016-0138-3