Storage container for radioactive material

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

Reexamination Certificate

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Details

C422S903000, C588S016000, C588S018000, C264S255000

Reexamination Certificate

active

06699439

ABSTRACT:

BACKGROUND OF THE INVENTION
1. Field of the Invention
It has been known for a spent nuclear reactor fuel assembly with fuel rods that contain radioactive nuclear fuel in a cladding tube, which represents a tightly enclosed capsule, to be filled with copper granulate among the fuel rods and then to form a container of copper sheet-metal, sealed in gas-tight fashion, around the nuclear reactor fuel assembly at high temperatures and high pressure. The gas-tightly sealed container is placed in a drilled hole in granite at an ultimate storage site, and the hole is filled with bentonite clay as a barrier to radioactive emitters (radionuclides). The copper granulate in the sheet copper container is intended to lend mechanical stability to the container.
2. Summary of the Invention
It is accordingly an object of the invention to provide a container with a radioactive body, which overcomes the disadvantages of the prior art devices and methods of this general type and which is improved with regard to the retention capability of the barriers formed for radioactive emitters (radionuclides). Specifically, it is an object to further improve the radioactive retention of the cladding tubes of the fuel rods and of the container.
With the foregoing and other objects in view there is provided, in accordance with the invention, an ultimate storage container assembly, comprising a gas-tight container, a plurality of spent fuel rods gas-tightly enclosed in the container, and a bulk fill of zeolite and/or activated charcoal embedding the spent fuel rods in the container.
Except for noble gases, zeolite and/or activated charcoal absorb or adsorb nonvolatile or readily volatile radionuclides and thus make it possible to drastically reduce the radioactivity released in the case of a leak in the cladding tubes. This is especially true for radioactive iodine, cesium and strontium. That is, zeolite and/or activated charcoal relieve the barrier function of the container for radioactive emitters (radionuclides).
The bulk fill of zeolite and/or activated charcoal in the container also leaves enough empty space to receive noble gases that are released. Accordingly, excessively high internal pressure cannot build up in the container.
Nevertheless, the bulk fill of zeolite and/or activated charcoal has sufficient thermal conductivity to dissipate the heat of decay, or afterheat, from the fuel rods. The bulk fill also represents additional thermal capacity in the container. The bulk fill, especially if it contains activated charcoal, also has a good moderating effect on neutrons and therefore reduces the hardness of neutron radiation that can be emitted by the radioactive substance in the fuel rods. The bulk fill can also contribute to shielding gamma radiation that originates in the fuel rods. Finally, the bulk fill also acts as a mechanical buffer for the fuel rods supported in the container. These fuel rods are protected by the bulk fill against damage when the container is being transported or manipulated. Radionuclides absorbed by the bulk fill change into states of equilibrium, in response to chemical laws, and thereby lose their tendency to migrate, so that the bulk fill reliably assures long-term storage of the capsules.
In accordance with an added feature of the invention, the container is formed with steel walls and steel plates welded in gas-tight fashion to the steel walls.
In accordance with another feature of the invention, a fuel assembly encloses the fuel rods and the fuel assembly is penetrated by the bulk fill. The container may be dimensioned to house a single the fuel assembly.
In accordance with an additional feature of the invention, the bulk fill is formed of granulate material.
Furthermore, additional bulk fill selected from the group consisting of zeolite and activated charcoal may surround the container.
In accordance with a further feature of the invention, the zeolite is type A zeolite, preferably selected from the group consisting of MgA, CaA, and SrA. Further, the zeolite may be doped with silver.
Preferred zeolites are chabazite and mordenite.
In accordance with a concomitant feature of the invention, particles are admixed in the bulk fill, the particles being selected from the group consisting of metal grit, MnO
2
, Al
2
O
3
, MgO, SnO
2
, ZrO
2
, and silicate.
Other features which are considered as characteristic for the invention are set forth in the appended claims.
Although the invention is illustrated and described herein as embodied in a container with a radioactive body, it is nevertheless not intended to be limited to the details shown, since various modifications and structural changes may be made therein without departing from the spirit of the invention and within the scope and range of equivalents of the claims.
The construction and method of operation of the invention, however, together with additional objects and advantages thereof will be best understood from the following description of specific embodiments when read in connection with the accompanying drawings.


REFERENCES:
patent: 4778628 (1988-10-01), Saha et al.
patent: 4891164 (1990-01-01), Gaffney et al.
patent: 4950426 (1990-08-01), Markowitz et al.
patent: 5169566 (1992-12-01), Stucky et al.
patent: 0 049 936 (1982-04-01), None
patent: 0 245 912 (1987-11-01), None
patent: 0 319 398 (1989-06-01), None
Excerpt from Ullmann's Encyclopedia of Technical Chemistry, vol. 17 “Molecular Sieve” (Puppe, Dr. L.) In German.
Excerpt from Ullmann's Encyclopedia of Technical Chemistry, vol. 24 “Zeolites” (Mengel, Dr. M.) dated 1983 In German.
Russian Patent Abstract SU 1299369 A1 (Boltenko et al.) dated Jul. 26, 1985.
Japanese Patent Abstract JP63177099 A (Kajima).

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