Method for immobilizing irradiated graphite
By grinding and cementing irradiated graphite with titanium dioxide at room temperature, the method addresses the complexity and emissions of existing methods, providing a simplified and effective immobilization solution for radioactive waste.
Patent Information
- Authority / Receiving Office
- UA · UA
- Patent Type
- Utility models
- Current Assignee / Owner
- INSTITUTE FOR SAFETY PROBLEMS OF NUCLEAR POWER PLANTS
- Filing Date
- 2026-02-23
- Publication Date
- 2026-07-08
AI Technical Summary
Existing methods for immobilizing radioactive waste from irradiated graphite in nuclear facilities require special equipment and high temperatures, leading to complex technological designs and potential radioactive emissions.
The method involves grinding irradiated graphite into blocks or cylinders, adding powdered titanium dioxide to form a cement matrix at room temperature, and shaping into cubes before storage, eliminating high-temperature synthesis and gaseous emissions.
This approach simplifies the technological process and prevents the release of radioactive isotopes into the atmosphere, reducing equipment complexity and emissions.
Abstract
Description
The utility model relates to methods for immobilizing radioactive waste. The method can be used in the decommissioning of nuclear facilities with graphite moderator. A known method of immobilizing radioactive waste [Ukrainian Patent No. 134617, published 05 / 27 / 2019], in which crushed irradiated graphite is loaded into a reactor with an electrothermal fluidized bed, into which, to create it and to carry out pyrolysis, hydrocarbon gas. Then, a current is passed through the fluidized bed of radioactive material, thereby heating it. At a temperature of 900-1600 °C, the pyrocarbon precipitation process is carried out by pyrolysis of hydrocarbon gas, in which pyrocarbon is precipitated onto radioactive particles material. After that, the radioactive material bound by pyrocarbon is cooled, unloaded and delivered to the place of further use or disposal. This method requires special equipment and high temperatures, which significantly complicates its use. The closest is the method of processing solid high-level graphite-containing waste [Patent RF No. 2065220, published 10.08.1996], which includes grinding of graphite-containing waste, introduction titanium and / or aluminum as an energy carrier, titanium dioxide and / or silicon dioxide as an oxide carbide-forming element, heat treatment of the prepared mixture in the mode high-temperature synthesis and subsequent compaction of synthesis products. This method produces gaseous products, which creates additional radioactive emissions. isotopes into the air atmosphere. The use of high-temperature synthesis complicates the technological design and use of the method. The utility model is based on the task of improving the method of immobilizing irradiated graphite, in which, as a result of the use of cementation, irradiated graphite is immobilized in cement matrix, which prevents the release of radioactive isotopes into the atmosphere. The absence of high-temperature synthesis greatly simplifies the technological process. design and use of the method. The problem is solved by the fact that in the method of immobilizing irradiated graphite, which includes grinding irradiated graphite, introduction of titanium dioxide, according to the utility model obtained The mixture is cemented into a cubic shape with a wall length of 0.15 meters and then moved into container for storing radioactive waste. Due to the combination of distinctive features, gaseous radioactive waste is not generated and The technological design and use of the method are simplified. The method of immobilizing irradiated graphite is carried out as follows: blocks and cylinders with irradiated graphite from a nuclear reactor is crushed, cemented with the addition of powdered titanium dioxide into a cubic shape with a wall length of 0.15 meters, after the cement has hardened The immobilized irradiated graphite is transferred to a radioactive waste storage container. The cementing process is carried out at a temperature of 15…25 °C. Example 1 (by closest analogue): The irradiated graphite is crushed, then titanium and / or aluminum are introduced as an energy carrier, dioxide titanium and / or silicon dioxide as the oxide of the carbide-forming element, heat treatment is carried out of the prepared mixture in the high-temperature synthesis mode and compact the synthesis products. Gaseous products are formed, which creates additional emissions of radioactive isotopes in the air atmosphere. The use of high-temperature synthesis complicates the technological design and use of the method. Example 2 (according to the proposed method): Blocks and cylinders of irradiated graphite are crushed, cemented with the addition of powdered titanium dioxide into a cubic shape with a wall length of 0.15 meters, after hardening cement, the immobilized irradiated graphite is transferred to a container for storing radioactive waste. Gaseous radioactive waste is not generated and the technological design and using the method.
Claims
A method of immobilizing irradiated graphite, comprising grinding irradiated graphite, introduction of titanium dioxide, which is characterized in that the resulting mixture is cemented in cubic shape with a wall length of 0.15 meters, followed by transfer to a container for storage of radioactive waste.