Continuous dissolution apparatus for spent nuclear fuel

Induced nuclear reactions: processes – systems – and elements – Fission reactor material treatment – Impurity removal

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134 3, 134 94, 252626, 252627, 252630, 376261, 376272, 376308, 422903, G21C 1942, G21F 900, G21F 902, C23G 102

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active

048349364

ABSTRACT:
A continuous dissolution apparatus for spent nuclear fuel in which a container (2) for holding a dissolution processing solution (1) is continuously supplied with nitric acid from a feed port (3), while the processing solution is continuously drawn out from an outlet (4). Baskets (71-74) in the container are packed with spent-fuel chops (6), which are continuously dissolved by the processing solution. The container is provided with a solution reserving section (4) for lowering the concentration of radioiodine contained in the dissolution processing solution, and a partition wall (10) is formed between the solution reserving section and a container body. The dissolution processing solution having overflowed from the upper edge of the partition wall flows into the solution reserving portion (14) through a perforated plate column (11). The solution reserving portion is furnished with a heating coil (12) for heating the dissolution processing solution and generating steam, and a gas blow pipe (13) for injecting an inert or nitrogen oxide gas into the solution. Thus, elementary iodine within the dissolution processing solution of the solution reserving section is expelled from the off-gas outlet (5) of the container together with the steam, and the radioiodine concentration in the dissolution processing solution of the solution reserving section can be lowered.

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patent: 4636362 (1987-01-01), Leister
Management of Gaseous Wastes from Nuclear Facilities, International Atomic Energy Agency, Vienna, 1980, pp. 139-156.

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