Some results of an investigation and prospects for the development of a high-temperature power reactor with a solid coolant

A validation of the possibility of developing and the basic advantages of a high-temperature nuclear reactor where the first-loop coolant is a solid are presented. The basic requirements for a solid coolant are formulated, a technology for fabricating spherical graphite particles by gas-phase pyroly...

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Veröffentlicht in:Atomic energy (New York, N.Y.) N.Y.), 2005-11, Vol.99 (5), p.792-798
Hauptverfasser: DENISKIN, V. P, DMITRIEV, A. M, NALIVAEV, V. I, FEDIK, I. I, ERMAKOV, N. I, MUSAELYAN, R. N
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Sprache:eng
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