Apparatus to recover tritium from tritiated molecules

Chemical apparatus and process disinfecting – deodorizing – preser – Chemical reactor – For radioactive reactant or product

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G21F 906, B01D 5928, C01B 310

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active

047626852

ABSTRACT:
An apparatus for recovering tritium from tritiated compounds is provided, including a preheater for heating tritiated water and other co-injected tritiated compounds to temperatures of about 600.degree. C. and a reactor charged with a mixture of uranium and uranium dioxide for receiving the preheated mixture. The reactor vessel is preferably stainless steel of sufficient mass so as to function as a heat sink preventing the reactor side walls from approaching high temperatures. A disposable copper liner extends between the reaction chamber and stainless steel outer vessel to prevent alloying of the uranium with the outer vessel. The uranium dioxide functions as an insulating material and heat sink preventing the reactor side walls from attaining reaction temperatures to thereby minimize tritium permeation rates. The uranium dioxide also functions as a diluent to allow for volumetric expansion of the uranium as it is converted to uranium dioxide.

REFERENCES:
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patent: 4297165 (1981-10-01), Breuckner
patent: 4370298 (1983-01-01), Marwick et al.
M. Hadzisehovic et al., "Possibility of Application of Metallic Uranium as a Reducing Agent for Tritiated Water", Nuclear Instruments & Methods, pp. 73-74, 1973.
Bartlit et al., "Engineering Problems of Fusion Research", Proceedings of Ninth Symposium, Chicago, IL, IEEE 1981, pp. 2084-2087.
Anderson et al., "Vacuum Applications for the Tritium Systems Test Assembly", J. Vac. Sci. Technol. A 1(2), Apr.-Jun. 1983, pp. 849-855.
R. E. Wilson et al., "Isothermal Reaction of Uranium with Steam Between 400 & 1600.degree. C.", Nucl. Sci. & Eng. vol. 25, pp. 109-115, 1966.
V. K. Gabrielson, SAHARA: A Multidimensional Heat Transfer Computer Code, Sandia National Laboratories SCL-DR-720024, pp. 3-88, Sep. 1972.

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