Abstract

The invention relates to devices for providing radiation safety. A shielding system for protecting against radiation consists of hollow modules which are connected to one another and form a shield. Each of the modules has at least one opening for filling the module with a filler. Each of the modules is a container made of sheet material. The outer wall and the inner wall of the container are radially curved and parallel. The side walls of the container in cross section have protrusions. On one of the side walls, part of the protrusion is a continuation of the outer wall. On the other side wall, part of the protrusion is a continuation of the inner wall. The protrusions are hollow and are part of the container. The invention makes it possible to simplify the design of a prefabricated shielding system by reducing the number of component parts, reducing the area occupied by a shield and reducing the space between a shield and a reservoir.

IPC Classes  ?

• G21F 5/00 - Transportable or portable shielded containers
• G21F 3/04 - BricksShields made up therefrom

Abstract

The invention relates to liquid radioactive waste (LRW) reprocessing technology and can be used for the recycling of radioactive substances at various nuclear industry sites. The technical result of the claimed invention involves increasing the efficiency of a method for reprocessing liquid radioactive waste by reducing the volume of radioactive waste requiring special storage and lowering the radiation exposure of service personnel during the reprocessing of liquid radioactive waste. The claimed technical result is achieved by the fact that a method of purifying liquid radioactive waste includes filtration, oxidation of liquid radioactive waste to obtain an oxidised flow, filtration of said flow, microfiltration and removal of radionuclides by feeding the filtrate into a vessel with granulated selective sorbents, wherein after oxidation, prior to filtration, a selective sorbent is introduced into the oxidised flow, wherein the sorbent is introduced into the liquid radioactive waste only after the oxidation stage.

IPC Classes  ?

• G21F 9/04 - Treating liquids

Abstract

The invention relates to medicine and veterinary science, and is a pharmaceutical composition which contains iron(II) sulphate and is intended for the treatment of iron deficiency anaemia, characterised in that it additionally contains iron hexacyanoferrate, iron-potassium hexacyanoferrate, potassium sulphate and microcellulose, said composition containing these ingredients in a defined ratio in wt.%. The invention provides for high therapeutic efficacy, good tolerance, and low toxicity.

IPC Classes  ?

• A61K 33/26 - IronCompounds thereof
• A61K 47/38 - CelluloseDerivatives thereof
• A61P 7/06 - Antianaemics

Abstract

The invention "Method for deactivating radioactive ion-exchange resins" relates to the field of radioactive waste treatment, and more particularly to the deactivation of spent ion-exchange resins (IER). The technical result of this invention consists in completely deactivating ion-exchange resins and minimizing the quantity of secondary radioactive waste that is formed. The technical result of the claimed invention is achieved in that spent radioactive ion-exchange resins are treated with solutions of alkali metal salts having a concentration of from 3 to 5 moles/liter and a pH of from 8 to 12, with the addition of an oxidizing agent as the IERs are simultaneously exposed to ultrasonic oscillations with an intensity of from 2 to 5 W/cm2 and a frequency of from 22 to 44 kHz at a temperature of from 50 to 80°С. The radioactive solution formed upon desorption is purified by selective sorbents placed in filtration columns. The deactivated ion-exchange resin is transferred to an industrial waste disposal site, and the deactivating solution, which is purified with selective sorbents, is sent, once its composition has been corrected, for re-use, i.e. for removing radionuclides from the next batch of IER.

IPC Classes  ?

• G21F 9/12 - Processing by absorptionProcessing by adsorptionProcessing by ion-exchange

Abstract

The invention relates to technology for managing liquid radioactive waste (LRW) from the nuclear fuel cycle, and can be used in the process of reprocessing LRW. The technical result of the claimed invention is that of increasing the radiation protection of workers during said process. The claimed method for reprocessing liquid radioactive waste includes separating sludges, colloids and particulates from a liquid phase and removing radionuclides from the liquid phase using selective sorbents, for which purpose a powdered selective sorbent is added under agitation to liquid radioactive waste contained in a tank, the liquid phase, purified of radionuclides, is then filtered by pumping same through a filter element situated at the outlet of the tank, which separates insoluble matter from the liquid phase, and then a curing agent is introduced into the tank to cure the contents thereof, wherein the stages of pumping LRW into the tank, mixing the waste with a sorbent and removing the purified solution are repeated several times prior to curing of the sorbent inside the tank.

IPC Classes  ?

• G21F 9/04 - Treating liquids
• G21F 9/12 - Processing by absorptionProcessing by adsorptionProcessing by ion-exchange

Abstract

Use: for processing liquid radioactive waste. Essence of the invention: taking liquid radioactive waste having a complex salt composition, including waste containing complexing agents, and introducing into same a cobalt decomplexation agent and a sulphide-containing substance, and separating radioactive sediment from the solution, wherein the cobalt decomplexation agent consists of a soluble nickel (II) salt which is introduced into the liquid radioactive waste having a pH of 3 to 12, together with a sorbent which is selective to cesium and which is based on a ferrocyanide of a transition metal, mixing the solution for no less than 1 hour, introducing a sulfide-containing substance into same, and mixing the suspension for no less than 0.5 hours. The invention allows for increasing the efficiency of a method by means of simplifying same, providing for a high level of radionuclide removal from LRW, said radionuclides having a complex chemical and radiochemical composition, with a wide range in the pH of initial solutions.

IPC Classes  ?

• G21F 9/06 - Processing
• G21F 9/12 - Processing by absorptionProcessing by adsorptionProcessing by ion-exchange

Abstract

The invention relates to techniques for treating materials containing a radioactive contaminant, and may be used in the purification of the liquid radioactive waste (LRW) that accumulates and forms during operation of nuclear power plants and other facilities of the nuclear cycle. The technical result of the claimed invention consists in lowering the radiation exposure of operating personnel during the LRW purification process, simplifying the technique of LRW purification, and improving the reliability and safety of the LRW purification process. In order to achieve this technical result, a method for purifying liquid radioactive waste is proposed which involves feeding the liquid radioactive waste into a container, introducing sorbents into said container, mixing the liquid radioactive waste and the sorbents in the container, and separating spent sorbent from the solution, wherein the sorbent is added to the container in a wrapping made from materials that are soluble in an aqueous medium.

IPC Classes  ?

• G21F 9/04 - Treating liquids
• G21F 9/12 - Processing by absorptionProcessing by adsorptionProcessing by ion-exchange

Abstract

The invention relates to techniques for cementing materials with radioactive components and may be used in processing liquid radioactive waste (LRW) which accumulate and form during the operation of nuclear power plants and other facilities of the nuclear cycle. The technical result of the claimed invention consists in decreasing the dose load on service personnel during the process of conditioning liquid radioactive waste, simplifying the LRW conditioning process, and enhancing the reliability and safety of the LRW conditioning process. In order to achieve said technical result, a method is proposed for conditioning liquid radioactive waste, including feeding liquid radioactive waste into an LRW cementing container, feeding cement with additives into the LRW cementing container, mixing the cement with additives and the liquid radioactive waste until achieving full homogenization, wherein the cement with additives is fed into the LRW cementing container in a package made of materials which are soluble in an aqueous medium.

IPC Classes  ?

• G21F 9/04 - Treating liquids
• G21F 9/16 - Processing by fixation in stable solid media

Abstract

The invention relates to a technique for handling liquid radioactive waste from a nuclear fuel-energy cycle, and may be used in a process for processing liquid radioactive waste for maximally reducing the volume thereof and removing radionuclides by concentrating same in a solid phase. The described invention solves the problem of better-protecting service personnel against radiation during a production process, and specifically: decreasing the dose load to personnel when processing liquid radioactive waste, simplifying the technological process (avoiding the use of an expensive and difficult-to-operate radioactive waste cementing installation, decreasing the number of other apparatuses requiring special servicing, decreasing the amount of secondary waste), and producing, as a result of liquid radioactive waste processing, a final product (block) which is safe to transport, store and utilize. The aim is achieved by means of a method for processing liquid radioactive waste and for the recovery thereof, including waste oxidation, separating sludge, colloids and suspended particles from a liquid phase, and removing, from the liquid phase, radionuclides to be subsequently recovered using selective sorbents and filters; the method is characterized in that, prior to the stage for separating sludge, colloids and suspended particles from the liquid phase of the radioactive waste, selective sorbents in the form of powders are added and mixed into the liquid waste.

IPC Classes  ?

• G21F 9/04 - Treating liquids
• G21F 9/20 - Disposal of liquid waste

Abstract

The group of inventions relates to constructing structures, such as the buildings of nuclear power plants, which are erected from monolithic blocks or slabs made of concrete or reinforced concrete. A block or a slab contains a built-in container with components for the sorption extraction, from water, of radionuclides or toxic substances. The container has elements for feeding-in contaminated water and for evacuating treated water. An erection method includes building a structure using the said blocks or slabs. A method for manufacturing a building block or slab includes forming a body out of concrete, embedding into same at least one container having water-treatment components, and having fittings or flanges for feeding-in contaminated water and for evacuating treated water. The invention provides for safe operations when erecting structures, and prevents the spread of radionuclides beyond the boundaries of a structure.

IPC Classes  ?

• G21D 7/00 - Arrangements for direct production of electric energy from fusion or fission reactions
• E04C 1/40 - Building elements of block or other shape for the construction of parts of buildings built-up from parts of different materials, e.g. composed of layers of different materials or stones with filling material or with insulating inserts
• E04H 5/02 - Buildings or groups of buildings for industrial purposes, e.g. for power-plants or factories
• G21F 9/06 - Processing