A passive venting arrangement for use in venting of gases produced by radioactive materials includes a source gas region for receiving the gases produced by the radioactive materials; a filter ullage region disposed above the source gas region and segregated therefrom except for a plurality of bore holes which each extend between, and fluidly couple, the source gas region and the filter ullage region; and a plurality of filters disposed in contact with the filter ullage region, wherein each filter is structured to provide for the exchange of gases from the filter ullage region through the filter to an ambient environment.

The invention provides a reactor containment vessel vent system capable of continuously releasing steam generated in a reactor containment vessel to the atmosphere even when a power supply is lost. In the reactor containment vessel vent system (15), the noble gas filter (23) that allows steam to pass through but does not allow radioactive noble gases to pass through among vent gas discharged from the reactor containment vessel (1) is provided at a most downstream portion of the vent line. An immediate upstream portion of the noble gas filter (23) and the reactor containment vessel (1) are connected to each other by the return pipe (24a, 24b) via the intermediate vessel (100). Further, when the radioactive noble gases having pressure equal to or higher than predetermined pressure stays in the immediate upstream portion of the noble gas filter (23), the staying radioactive noble gases flows into the intermediate vessel (100) by the relief valve (25). Thus, the noble gas filter (23) does not lose steam permeability, and the reactor containment vessel vent system (15) can continuously release the steam to the atmosphere.

The invention provides a reactor containment vessel vent system capable of continuously releasing steam generated in a reactor containment vessel to the atmosphere even when a power supply is lost. In the reactor containment vessel vent system (15), the noble gas filter (23) that allows steam to pass through but does not allow radioactive noble gases to pass through among vent gas discharged from the reactor containment vessel (1) is provided at a most downstream portion of the vent line. An immediate upstream portion of the noble gas filter (23) and the reactor containment vessel (1) are connected to each other by the return pipe (24a, 24b) via the intermediate vessel (100). Further, when the radioactive noble gases having pressure equal to or higher than predetermined pressure stays in the immediate upstream portion of the noble gas filter (23), the staying radioactive noble gases flows into the intermediate vessel (100) by the relief valve (25). Thus, the noble gas filter (23) does not lose steam permeability, and the reactor containment vessel vent system (15) can continuously release the steam to the atmosphere.

A container is designed to safely store radioactive debris. The container has an overpack having an elongated body extending between a top end and a bottom end. A basket is situated inside of the overpack. The basket has elongated canisters. Each of the canisters has an elongated body extending between a top end and a bottom end. At least one of the canisters has an insert with a plurality of elongated perforated tubes that contain radioactive debris. The perforations enable gas flow, primarily air, through the side wall to enable evaporation of liquid, primarily water, from the radioactive debris, by increasing the exposed surface area of the debris.

A container is designed to safely store radioactive debris. The container has an overpack having an elongated body extending between a top end and a bottom end. A basket is situated inside of the overpack. The basket has elongated canisters. Each of the canisters has an elongated body extending between a top end and a bottom end. At least one of the canisters has an insert with a plurality of elongated perforated tubes that contain radioactive debris. The perforations enable gas flow, primarily air, through the side wall to enable evaporation of liquid, primarily water, from the radioactive debris, by increasing the exposed surface area of the debris.

The invention relates to the reprocessing of spent ion-exchange resins at nuclear power plants or special plants. The invention involves microencapsulation of ion-exchange resins (immobilization of radionuclides inside microcapsules), reducing the volume of discharged ion-exchange resins and preventing their swelling when exposed to moisture. A method for treatment of spent ion-exchange resins for disposal comprises feeding a mixture of spent ion-exchange resins to the loading tank, separating the ion-exchange resins, feeding separated ion-exchange resins into the drying chamber, vacuum drying of the ion-exchange resins, unloading the treated ion-exchange resin into a transport container. The ion-exchange resins after vacuum drying are subjected to additional heat treatment in a high-temperature furnace and unloading treated ion-exchange resin in a transport container. The invention reduces the volume of unloaded ion-exchange resins by more than 2 times, ensuring their swelling no more than 10%, and preventing the immobilization of radionuclides inside microcapsules.

The invention relates to the reprocessing of spent ion-exchange resins at nuclear power plants or special plants. The invention involves microencapsulation of ion-exchange resins (immobilization of radionuclides inside microcapsules), reducing the volume of discharged ion-exchange resins and preventing their swelling when exposed to moisture. A method for treatment of spent ion-exchange resins for disposal comprises feeding a mixture of spent ion-exchange resins to the loading tank, separating the ion-exchange resins, feeding separated ion-exchange resins into the drying chamber, vacuum drying of the ion-exchange resins, unloading the treated ion-exchange resin into a transport container. The ion-exchange resins after vacuum drying are subjected to additional heat treatment in a high-temperature furnace and unloading treated ion-exchange resin in a transport container. The invention reduces the volume of unloaded ion-exchange resins by more than 2 times, ensuring their swelling no more than 10%, and preventing the immobilization of radionuclides inside microcapsules.

There is provided an organic iodine trapping apparatus that can efficiently trap an organic iodine without using complicated or large equipment. An organic iodine trapping apparatus 30 is an apparatus that traps an organic iodine, including: a trapping vessel 1 through which gas containing an organic iodine is passed; an organic iodine remover 2 (Example: trihexyl (tetradecyl) phosphonium chloride, or the like) that is disposed in or injected into the trapping vessel 1 and decomposes the organic iodine; and a trapping material 3 that is disposed in or injected into the trapping vessel 1 and traps iodine ions generated by decomposition of the organic iodine, in which the trapping material 3 is a metal (Example: silver or the like) or a metal compound (Example: silver chloride, silver oxide, or the like).

Provided is a method for treating radioactive iodine contained in steam discharged from a nuclear power facility, including a filling step of filling an air-permeable container with a granulated radioactive iodine adsorbent of zeolite X, wherein ion exchange sites of the zeolite X are substituted with silver so that a size of minute pores of the zeolite X is suited to a size of a hydrogen molecule, and the radioactive iodine adsorbent has a silver content of 36 wt % or more when dried, a particle size of 10×20 mesh, a hardness of 94% or more, and a water content of 12 wt % or less when dried at 150° C. for 3 h and thereby reduced in weight; and a flow passing step of passing a flow of the steam discharged from the nuclear power facility, through the container filled with the radioactive iodine adsorbent.

Provided is a method for treating radioactive iodine contained in steam discharged from a nuclear power facility, including a filling step of filling an air-permeable container with a granulated radioactive iodine adsorbent of zeolite X, wherein ion exchange sites of the zeolite X are substituted with silver so that a size of minute pores of the zeolite X is suited to a size of a hydrogen molecule, and the radioactive iodine adsorbent has a silver content of 36 wt % or more when dried, a particle size of 10×20 mesh, a hardness of 94% or more, and a water content of 12 wt % or less when dried at 150° C. for 3 h and thereby reduced in weight; and a flow passing step of passing a flow of the steam discharged from the nuclear power facility, through the container filled with the radioactive iodine adsorbent.