Provided herein is a process for removal of 99Tc from liquid intermediate level waste (ILW) of spent fuel reprocessing including the steps of: adding HNO.sub.3 to ILW till the pH is 2 to destroy the carbonates, transferring the ILW derived of carbonates to a tank containing mild steel wool(msw) for 4 to 48 hrs, subjecting the ILW and MS Wool to the step of separation, discharging the supernatant solution free of 99Tc and retaining the corrosion products (goethite(FeOOH/magnetite), subjecting the said corrosion products to the step of vitrification, and storing the said vitrified 99Tc bearing waste.

Techniques for testing subterranean water for one or more radioactive isotopes for a hazardous waste material repository include collecting, from a test drillhole formed from a terranean surface to a subterranean formation, a subterranean water sample from the subterranean formation; determining, with an accelerator mass spectrometry (AMS) system, a concentration of a radioactive isotope of an element in the subterranean water sample relative to a stable isotope of the element in the subterranean water sample; comparing the determined concentration of the radioactive isotope of the element in the subterranean water sample with a concentration of the radioactive isotope of the element in a surface water sample relative to the stable isotope of the element in the surface water sample; and based on the determined concentration of the radioactive isotope in the subterranean water sample being a specified percentage of the concentration of the radioactive isotope in the surface water sample, determining that the subterranean formation is a hazardous waste storage repository.

A bath electrical heating device for deactivation designed to provide heating of bath deactivation and the deactivating solution in it before deactivation of reactor facility equipment and ensuring the removal of excess heat in the process of deactivation. The invention improves reliability, reduces the material consumption of the device and simplifies the structure installation and repair. The device performs at least from three heat insulation blocks in the form of coaxial metal screens, installed with an air gap from the heater. The heater with current leads is made in hermetic perform, each heat insulation blocks supplemented with an air-gap coaxial metal protective casing. The air gap of which in the upper part is covered with a cap with a visor whose diameter exceeds the external diameter of the protective casing, wherein solid cover of the upper protective casing install a sealed coupling.

A device for repairing damage to a bottom of a container filled with water is disclosed. The device comprises a guiding device, which can be placed on the bottom of the container and which has a centering device for centering the guiding device between wall sections of the bottom elements. The devices further comprises a fixing device for fixing the guiding device on the bottom of the container, a carrier, which can be guided along the guiding device and on which at least one pivot arm is arranged, and an accommodating element arranged at a free end of the pivot arm, for accommodating adhesive, with which part of a wall section of the bottom elements can be covered.

A device for repairing damage to a bottom of a container filled with water is disclosed. The device comprises a guiding device, which can be placed on the bottom of the container and which has a centering device for centering the guiding device between wall sections of the bottom elements. The devices further comprises a fixing device for fixing the guiding device on the bottom of the container, a carrier, which can be guided along the guiding device and on which at least one pivot arm is arranged, and an accommodating element arranged at a free end of the pivot arm, for accommodating adhesive, with which part of a wall section of the bottom elements can be covered.

Disclosed herein is a nuclear power plant main steam system, which reduces the atmospheric discharge of radioactive materials generated in an accident, the system including: a decontamination water tank containing decontamination water; and a connection pipe for connecting the decontamination water tank from a main steam pipe which connects a steam generator and a turbine, wherein the connection pipe is connected to the decontamination water tank through a main steam safety valve or a connection valve, wherein the main steam safety valve or the connection valve is configured by a three-way valve and is configured to discharge the generated steam to the air when an accident occurs within a design basis and to transfer the generated steam to the decontamination water tank when a severe accident occurs. A main steam system according to the present invention has an effect of reducing discharge of radioactive materials to the air when a containment bypass accident including a steam generator tube rupture caused by high-temperature steam occurs.

An activating agent for the treatment of radioactive wastewater. The activating agent is prepared by dissolving a mixture of inorganic salts including Ca.sup.2+, Na.sup.+, Sr.sup.2+, Zn.sup.2+, Mg.sup.2+, Fe.sup.2+ and K.sup.+ in pure water having an electrical resistivity greater than 0.5 M.Math.cm to yield a solution. A method of radioactive wastewater treatment using the activating agent includes: 1) preparing the activating agent; 2) adding the activating agent to radioactive wastewater having an electrical resistivity greater than 0.5 M.Math.cm; uniformly mixing the activating agent and the radioactive wastewater; 3) further treating the radioactive wastewater including the activating agent using an electro-deionization device; and 4) collecting two liquid flows obtained in 3), one being purified water, the other being concentrated water returning to 2) for further purification.

Techniques for testing subterranean water for one or more radioactive isotopes for a hazardous waste material repository include collecting, from a test drillhole formed from a terranean surface to a subterranean formation, a subterranean water sample from the subterranean formation; determining, with an accelerator mass spectrometry (AMS) system, a concentration of a radioactive isotope of an element in the subterranean water sample relative to a stable isotope of the element in the subterranean water sample; comparing the determined concentration of the radioactive isotope of the element in the subterranean water sample with a concentration of the radioactive isotope of the element in a surface water sample relative to the stable isotope of the element in the surface water sample; and based on the determined concentration of the radioactive isotope in the subterranean water sample being a specified percentage of the concentration of the radioactive isotope in the surface water sample, determining that the subterranean formation is a hazardous waste storage repository.

Disclosed are an apparatus and a method for supplying a pulse to solvent extraction column (hereinafter, pulsed column). More particularly, the present invention relates to a low cost apparatus with a simple method for stably supplying a pulse to a pulsed column, which is employed as unit equipment in a solvent extraction process. The apparatus for supplying a pulse to the pulsed column having a first solvent inlet and a second solvent outlet at the low part of the pulsed column, and a second solvent inlet and a first solvent outlet at the top part of the pulsed column thereof, includes: a diaphragm pump actuated by using electric power or compressed air, and having a discharge part and a suction part, in which one of the discharge part and the suction part is blinded while the remaining one thereof is connected to the pulsed column via a pulse supply line.

Disclosed are an apparatus and a method for supplying a pulse to solvent extraction column (hereinafter, pulsed column). More particularly, the present invention relates to a low cost apparatus with a simple method for stably supplying a pulse to a pulsed column, which is employed as unit equipment in a solvent extraction process. The apparatus for supplying a pulse to the pulsed column having a first solvent inlet and a second solvent outlet at the low part of the pulsed column, and a second solvent inlet and a first solvent outlet at the top part of the pulsed column thereof, includes: a diaphragm pump actuated by using electric power or compressed air, and having a discharge part and a suction part, in which one of the discharge part and the suction part is blinded while the remaining one thereof is connected to the pulsed column via a pulse supply line.