Maximal design basis accident of fusion neutron source DEMO-TIN

When analyzing the safety of nuclear (including fusion) facilities, the maximal design basis accident at which the largest release of activity is expected must certainly be considered. Such an accident is usually the failure of cooling systems of the most thermally stressed components of a reactor (...

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Bibliographic Details
Published in:Physics of atomic nuclei 2015-12, Vol.78 (10), p.1128-1133
Main Author: Kolbasov, B. N.
Format: Article
Language:English
Subjects:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Analysis
CONCENTRATION RATIO
COOLING SYSTEMS
DESIGN BASIS ACCIDENTS
DIVERTORS
FAILURES
FIRST WALL
FISSION PRODUCTS
HEAVY ION FUSION REACTIONS
HYDROGEN
Ionizing radiation
ITER TOKAMAK
MOLTEN SALT FUELS
NEUTRON SOURCES
Particle and Nuclear Physics
Physics
Physics and Astronomy
RADIOACTIVITY
REMOVAL
STRESSES
THERMONUCLEAR REACTIONS
TRITIUM
VANADIUM CARBIDES
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Summary:When analyzing the safety of nuclear (including fusion) facilities, the maximal design basis accident at which the largest release of activity is expected must certainly be considered. Such an accident is usually the failure of cooling systems of the most thermally stressed components of a reactor (for a fusion facility, it is the divertor or the first wall). The analysis of safety of the ITER reactor and fusion power facilities (including hybrid fission–fusion facilities) shows that the initial event of such a design basis accident is a large-scale break of a pipe in the cooling system of divertor or the first wall outside the vacuum vessel of the facility. The greatest concern is caused by the possibility of hydrogen formation and the inrush of air into the vacuum chamber (VC) with the formation of a detonating mixture and a subsequent detonation explosion. To prevent such an explosion, the emergency forced termination of the fusion reaction, the mounting of shutoff valves in the cooling systems of the divertor and the first wall or blanket for reducing to a minimum the amount of water and air rushing into the VC, the injection of nitrogen or inert gas into the VC for decreasing the hydrogen and oxygen concentration, and other measures are recommended. Owing to a continuous feed-out of the molten-salt fuel mixture from the DEMO-TIN blanket with the removal period of 10 days, the radioactivity release at the accident will mainly be determined by tritium (up to 360 PBq). The activity of fission products in the facility will be up to 50 PBq.
ISSN:1063-7788
1562-692X
DOI:10.1134/S106377881510004X