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Title: Concept of a demonstrational hybrid reactor—a tokamak with molten-salt blanket for {sup 233}U fuel production: 1. Concept of a stationary Tokamak as a neutron source

On the basis of current understanding of physical processes in tokamaks and taking into account engineering constraints, it is shown that a low-cost facility of a moderate size can be designed within the adopted concept. This facility makes it possible to achieve the power density of neutron flux which is of interest, in particular, for solving the problem of {sup 233}U fuel production from thorium. By using a molten-salt blanket, the important task of ensuring the safe operation of such a reactor in the case of possible coolant loss is accomplished. Moreover, in a hybrid reactor with the blanket based on liquid salts, the problem of periodic refueling that is difficult to perform in solid blankets can be solved.
Authors:
; ; ;  [1]
  1. State Research Center of the Russian Federation, Troitsk Institute for Innovation and Fusion Research (Russian Federation)
Publication Date:
OSTI Identifier:
22471907
Resource Type:
Journal Article
Resource Relation:
Journal Name: Physics of Atomic Nuclei; Journal Volume: 78; Journal Issue: 12; Other Information: Copyright (c) 2015 Pleiades Publishing, Ltd.; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; BREEDING BLANKETS; HYBRID REACTORS; LIMITING VALUES; MOLTEN SALTS; NEUTRON FLUX; NEUTRON SOURCES; NUCLEAR ENGINEERING; REACTOR OPERATION; REACTOR SAFETY; TOKAMAK DEVICES; URANIUM 233