Pre-treatment method for radioactive metal waste

The present invention provides a pre-treatment method for facilitating a post-treatment by previously selecting radioactive metal wastes. That is, the radioactive wastes are selected depending on their kinds. Then, they are dried at a temperature in accordance with the kinds. For example, in the case of a zircaloy cladding tube (hull), tritium is absorbed and stored as a dangerous materials. However, since tritium has a characteristic that it is released abruptly at a temperature higher than 450degC, tritium is scarcely released if the metal wastes are dried at 150degC. Further, in the case of stainless steel, even if it is dried at 600degC, dangerous materials such as tritium are not released. Selected radioactive metal wastes other than the hull are dried at 600degC to attain stable metals excellent in corrosion resistance even if they contain zircaloy, stainless steel and other attendant materials than metals. In addition, a steam explosion is not induced. (I.S.)