Published May 1983 | Version v1
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Problems of tritium extraction from solid blankets

Creators

  • 1. CEA Centre d'Etudes Nucleaires de Saclay, Div. d'Etudes de Separation Isotopique et de Chimie Physique (France)

Description

Tritium extraction from fusion reactor blankets must regenerate tritium at an average rate equal to that of burning plus losses. This rate depends of parameters that will be discussed: A) Equilibrium values of vapor pressures lead to minimum sweeping rates requirements. They depend, through Sievert's constants, on tritium concentration in the blanket. The optimum value of this concentration is discussed using the formula n=f. j.p (n=ppm of T m blanket f = fraction of blanket treated j = days between extraction sup(1/)p = fraction of T extracted). B) The literature provides extraction rates of tritium from various materials. This enables an estimation of the inventory in the blanket through the relation I = tauP (I=inventory tau defined residence time of tritium P production rate of tritium). C) The blanket must be designed in such a way that tau is acceptable. Parameters of influence are concentration, discussed in A, but also temperature, structure of the blanket i.e. elementary radius of particles, specific surface, density, etc... in the case of solids. Relations between tau and those characteristics have yet to be subjected to experimental verifications. Minimum rates of sweeping, by extraction gases, have also to be investigated. Other important parameters of the design have an indirect influence on extraction rates, that should be kept in mind. Such as: total blanket volume, Li concentration and enrichment in 6Li. In addition the design of the extraction system must also be such that diffusion in the gas phase does not limit the rate of extraction. Finally if helium is used as coolant it's tritium content from leakage from the blanket and 23He capture of neutrons may require part of the coolant to be regularly processed with the extraction gas. (author).

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Part of:
Fusion Reactor Design and Technology. Vol. 2. Proceedings of the Third Technical Meeting

Additional details

Publishing Information

Publisher
IAEA
Imprint Place
Vienna (International Atomic Energy Agency (IAEA))
ISBN
92-0-131183-4
Imprint Title
Fusion Reactor Design and Technology. Vol. 2. Proceedings of the Third Technical Meeting
Imprint Pagination
502 p.
Series
Proceedings Series
Journal Page Range
p. 333-340
ISSN
0074-1884

Conference

Title
3. Technical Committee Meeting and Workshop on Fusion Reactor Design and Technology
Dates
5-16 Oct 1981
Place
Tokyo (Japan)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
53051816
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BREEDING BLANKETS; CONCENTRATION RATIO; DIFFUSION; ISOTOPE PRODUCTION; TRITIUM RECOVERY
Descriptors DEC
DIMENSIONLESS NUMBERS; REACTOR COMPONENTS

Optional Information

Notes
9 refs.; This record replaces 14773847 Imprint:In two volumes
Secondary number(s)
IAEA-TC--392/58