Abstract: In a method and an apparatus for dewatering and containing radioactive, aqueous waste (44), the latter is introduced into a filtration container (12) and is ultimately disposed of in a disposable container structure (12, 48, 50), which comprises the filtration container (12) holding the dewatered waste (44), as well as an outer container (50) enclosing the filtration container (12). The filtration container is an inner sack (12) having a bottom (13) which is provided with a straining cloth and through which essentially all the dewatering is carried out. After the dewatering operation has been completed, the inner sack (12) is sealed and placed in the outer container (50) in order to be ultimately disposed of. For purposes of cleaning, the filtration water (17) may be recirculated through the waste during the dewatering operation.
Abstract: The present invention relates to a method of solidifying radioactive waste with cement, comprising forming a mixture comprising water, a hydrophilic material and cement substantially non-shrinkable or expansible with respect to volume change upon hardening, mixing said mixture with the radioactive waste, followed by hardening to form a solid body.The present invention enables the formation of a compact solid body having voids, such as capillary voids, of reduced volume, which makes it possible to reduce the leaching rate of hazardous materials. Further, since no shrinkage accompanies hardening, no tensile stress occurs in the cement surrounding minute waste particles within the hardened material, thereby enabling a decrease in the strength of the solid body to be minimized. This in turn enables an increase in the amount of packing of waste. Prior addition of a hydrophilic material enables the cement fluidity before hardening to be maintained even after complete absorption of water by a water absorptive waste.
Abstract: A method and composition for stabilizing and isolating hazardous, radioactive or mixed waste materials of particulate and solid types, which comprises providing a non-toxic one component aqueous mixture of an acrylic polymer containing a thixotropic agent, a vinyl acetate-ethylene copolymer containing a thixotropic agent, or a vinyl chloride copolymer latex containing a thixotropic agent, and applying the mixture over surfaces of hazardous material in an amount sufficient to form a flexible impermeable coating or foam. The mixture may be applied by spraying to form a coating having a thickness of about 0.5 to about 5.0 centimeters when dry. The coated waste material may then be disposed of in conventional manner.
Abstract: The invention provides a method of recovering and storing radioactive iodine by a freeze vacuum drying process, in which off-gas generated when spent fuel is subjected to shearing and dissolving treatments is scrubbed and, when necessary, is subjected to a precipitation treatment by addition of additives, after which waste liquid containing radioactive iodine is freeze-dried by a freeze vacuum drying process to recover radioactive iodine as iodine compounds. As a result, since the radioactive iodine does not vaporize, release of the radioactive iodine into the environment can be eliminated. In addition, consumption of a collecting agent such as silver zeolite for collecting vaporized radioactive iodine can be reduced. The iodine compounds containing the recovered radioactive iodine is given the same composition as a stable, naturally occurring mineral and is solidified and mineralized as by a high-pressure press. This makes it possible to store long half-life .sup.
Type:
Grant
Filed:
August 15, 1991
Date of Patent:
October 12, 1993
Assignee:
Doryokuro Kakunenryo Kaihatsu Jigyodan
Inventors:
Katsuyuki Ohtsuka, Jin Ohuchi, Toru Suzuki