Patent Number: 050158635
Section: summary

FIELD OF THE INVENTION This invention relates to a radiation shield with an excellent heat-transferring property that covers a container containing radioactive wastes. Conventional shielding materials for neutrons and .gamma.-rays, such as polyethylene and lead, generally have low thermal conductivity. When a container containing exothermic radioactive wastes is covered with these shielding materials, therefore, the heat in the container does not radiate outside and the temperature in the container rises, possibly damaging the soundness of the wastes. This has so far imposed various restrictions on the amount of wastes contained and the design of containers. Explanation is given here of examples of three kinds of known shields applied to casks for the transportation and storage of spent nuclear fuels. (1) A cylindrical container proper that contains a spent nuclear fuel assembly is externally covered with a neutron or .gamma.-ray shield and the external surface of the shield, in turn, is covered with a shield cover. A large number of radiating fins whose ends are in contact with the external surface of the container body extend through the shield and shield cover up to the outside of the shield cover. (2) A cylindrical container body that contains a spent nuclear fuel assembly is externally covered with a neutron or .gamma.-ray shield and the external surface of the shield, in turn, is covered with a shield cover. A large number of radiating fins whose ends are in contact with the external surface of the container body extend through the shield nad shield cover up to the positionof the shield covr. (3) A cylindrical container body that contains a spent nuclear fuel assembly consists of an internal cylinder and an external cylinder, and the space between the internal and external cylinders is filled with a neutron- or .gamma.-ray-shielding material. For the radiation-shielding materials used in these examples, a powder of metal with high thermal conductivity (e.g. copperA) is often contained in the shielding materials to improve their thermal conductivyt, and/or the radiating fins are instralled inor through the shield to enhance their heat-transferring property, as mentioned above. These techniques, however, have some problems; for exaple, it is difficult to uniformly distribute the metal powder in the shield; it takes much time and labor to work the radiating fins and to install them in the container body; and neutrons stream through the radiating fins. Furthermore, it is pointed out that the decontamination property (ease of removing radiation contamination) is bad in the case of radiating fins described in paragraph 1). SUMMARY OF THE INVENTION Thus, the principal object of this invention is to provide a high-performance shielding material that combines the radiation-shielding function and an excellent heat-transferring property for the purpose of safely transporting and storing the exothermic radioactive wastes. This object is accomplished by providing composite particles obtained by coating minute particles having radiation-shielding property with a metal of high thermal conductivity and fabricating a radiation shield in a various shape from these composite particles. Included among methods of fabricating a radiation shield of excellent heat-transferring property from composite particles are, for example, a method involving forming composite particles into a wall-like body as a shield by hot-press forming (or cold-press forming), and a method involving closely packing the space between walls composing the shield body with composite particles. The core of a composite particle is made of a material selected from the group comprising polyethylene, polystyrene, polypropylene, bakelite, graphite, beryllium, oxides of beryllium, boron, compounds of boron, aluminum, oxides of aluminum, iron, ferroalloys, lead, lead alloys, gadolinium, oxides of gadolinium, cadmium, cadmium alloys, indium, indium alloys, hafnium, hafnium alloys, depleted uranium, and so on. The coating metal of high thermal conductivity is made of a material selected from the group comprising aluminum, aluminum alloys, beryllium, beryllium alloys, copper, copper alloys, iron, ferroalloys, silver, silver alloys, magnesium, magnesium alloys, molybdenum, molybdenum alloys, zinc, zinc alloys, tin, tin alloys, tungsten, tungsten alloys, iridium, iridium alloys, gold, and so on. The coating metal does not necessarily need to cover the whole surface of the core particle. It is desirable, however, to cover the whole surface in order to increase the thermal conductivity among composite particles by ensuring a large contact area of composite particles. It is recommended that the packing density of particles be 1 to 3 g/cm.sup.3, for example. According to the former method, i.e., the press forming method, composite particles are pressed to form a unit wall of appropriate size and this wall is attached to the container body. The deformation rate of composite particles, which depends on the materials used, is not very high because composite particles are minute. In a shield obtained by the press forming of composite particles or a shield obtained by packing the space between walls with composite particles, core particles shield radiations, such as neutrons and .gamma.-rays, emitted from exothermic radioactive wastes. On the other hand, the heat released from the radioactive waste in the container is transmitted through the container wall to the coating metal of composite particles which are in close contact with one another, and is released through this coating metal of high thermal conductivity to the external environment that surrounds the radioactive waste container. In other words, the radioactive shield on the basis of this invention is a high-performance shield that combines the radiation-shielding function and an excellent heat-transferring property. These and other features of this invention will become apparent from the description of the following embodiments with reference to the accompanying drawings.