Abstract: A transport/storage cask for a radioactive material has an inner shell, an outer shell and a circular gamma ray shielding layer and a circular neutron shielding layer both of which are placed between the inner shell and the outer shell. The gamma ray shielding layer is formed by aligning a plurality of gamma ray shielding blocks composed of lead in a block shape in the circumferential direction. The entire gamma ray shielding block in the axial direction is covered with a copper tube having a higher elasticity limit than the gamma ray shielding block. In the above transport/storage cask, the gamma ray shielding layer composed of lead or a lead alloy is not easily deformed.

Abstract: A method of producing biodiesel fuel from fats and oils includes a step of transesterification reaction in which fats and oils are transesterfied with lower alcohol, a step of fuel refining in which a resultant fatty acid alkyl ester produced in said transesterfication reaction step is refined, and a mixing step in which the fatty acid alkyl ester refined in the fuel refining step is mixed with light oil. The refined fatty acid alkyl ester is heated to a predetermined temperature and thus fused so as not to oxidize unsaturated fatty acids contained in the fatty acid alkyl ester, while the heated and refined fatty acid alkyl ester is mixed with light oil so as not to set the temperature of the mixed solution below the cold filter plugging point during the mixture, to dilute the fatty acid alkyl ester by light oil to a predetermined weight ratio.

Abstract: A transport/storage cask for a radioactive material has an inner shell, an outer shell and a circular gamma ray shielding layer and a circular neutron shielding layer both of which are placed between the inner shell and the outer shell. The gamma ray shielding layer is formed by aligning a plurality of gamma ray shielding blocks composed of lead in a block shape in the circumferential direction. The entire gamma ray shielding block in the axial direction is covered with a copper tube having a higher elasticity limit than the gamma ray shielding block. In the above transport/storage cask, the gamma ray shielding layer composed of lead or a lead alloy is not easily deformed.

Abstract: The invention provides a composite from which concrete featuring a sufficiently high heat resistance can be produced, as well as a high-safety sealed concrete cask having no opening (shielding defect) to offer high shielding performance that can prevent corrosion of an internal canister and release of radioactive material to the exterior. A concrete cask of the invention includes a cask body having a bottom but no lid in itself, and a lid which can open and close off a top opening of the cask body. Both the cask body and the lid are made of concrete manufactured by using a composite including Portland cement or blended cement containing Portland cement, which is mixed with water in such a manner that the content of calcium hydroxide falls in a range of 15% to 60% by mass after hardening through hydration reaction. Metallic heat-transfer fins are embedded in the cask body.

Abstract: It is an object of the present invention to obtain a containment concrete cask which has heat removal capacity maintained at the conventional level or beyond it and which prevents radiation from leaking to the outside. In a concrete cask, a shielding body composed of concrete and heat transfer fins made from metal are provided between an inner shell and an outer shell made from metal, and an accommodation portion for accommodating a radioactive substance is provided inside the inner shell. The accommodation portion has a containment structure to be insulated from the outside of the cask. In the heat transfer fins, the portions thereof at the outer shellside are provided in contact with the outer shell and the portions thereof at the inner shell side are cut so as to form a separation portion with respect to the inner shell.

Abstract: It is an object of the present invention to obtain a containment concrete cask which has heat removal capacity maintained at the conventional level or beyond it and which prevents radiation from leaking to the outside. In a concrete cask, a shielding body composed of concrete and heat transfer fins made from metal are provided between an inner shell and an outer shell made from metal, and an accommodation portion for accommodating a radioactive substance is provided inside the inner shell. The accommodation portion has a containment structure to be insulated from the outside of the cask. In the heat transfer fins, the portions thereof at the outer shellside are provided in contact with the outer shell and the portions thereof at the inner shell side are cut so as to form a separation portion with respect to the inner shell.

Abstract: The invention provides a composite from which concrete featuring a sufficiently high heat resistance can be produced, as well as a high-safety sealed concrete cask having no opening (shielding defect) to offer high shielding performance that can prevent corrosion of an internal canister and release of radioactive material to the exterior. A concrete cask of the invention includes a cask body having a bottom but no lid in itself, and a lid which can open and close off a top opening of the cask body. Both the cask body and the lid are made of concrete manufactured by using a composite including Portland cement or blended cement containing Portland cement, which is mixed with water in such a manner that the content of calcium hydroxide falls in a range of 15% to 60% by mass after hardening through hydration reaction. Metallic heat-transfer fins are embedded in the cask body.

Abstract: A cask for a radioactive material has a single gamma ray and neutron shielding layer disposed on the outside of a vessel body, and the shielding layer is formed of the compact of a mixture of lead and a metal hydride dispersed therein. This cask can exhibit an excellent shielding effect according to the balance of radiation source intensity between gamma rays and neutrons, and can be made more compact.

Abstract: A transport/storage cask for a radioactive material has an inner shell and an outer shell, and between the two shells, a gamma ray shielding layer and a neutron shielding layer are provided. The transport/storage cask also includes heat-conductive members which are provided so as to penetrate through the gamma ray shielding layer and the neutron shielding layer. The transport/storage cask for a radioactive material is capable of containing a radioactive material at an enhanced efficiency, exhibits excellent heat-conductive performance, and effectively shields gamma rays and neutrons.