Relevancy
The main idea of the program is to select and implement a technology for the treatment of solid radioactive waste (SRW) generated as a result of the decommissioning of the BN-350 reactor facility. To justify the selection and implementation of the SRW processing technology for the BN-350 reactor facility, at the first stage it is necessary to conduct a predictive assessment of the quantity of accumulated solid radioactive waste at the BN-350 reactor facility and to classify it according to type and activity level. At the second stage, proposals will be developed for selecting appropriate technologies for the processing of solid radioactive waste. At the third stage, the composition of matrices for different types of solid waste will be selected, and recommendations will be developed to optimize the stages of the immobilization technology for solid waste from the BN-350 reactor.
The relevance of this program lies in the fact that solving the stated tasks will result in the development of methodologies for studying the physicochemical properties of solid waste generated at the BN-350 reactor facility, according to their classification (activity and volume), as well as research results obtained using these methodologies. The main requirements for the composition, structure, and physicomechanical properties of matrices for SRW immobilization will be determined. A methodology for obtaining candidate matrix compositions and testing them for compliance with the established requirements will also be developed. The composition of matrices for different types of solid waste will be determined, and recommendations will be developed to optimize the stages of the immobilization technology for solid waste from the BN-350 reactor. In the future, this will make it possible to begin addressing the broader challenge of RW management in the nuclear industry and to ensure a scientific approach to the processing of SRW generated at the BN-350 reactor facility.
Implementation of the Program will enhance the competencies of the National Nuclear Center of the Republic of Kazakhstan (NNC RK) in the field of solid radioactive waste management and expand the regulatory and legal framework governing SRW management, particularly for bringing such waste into a conditionally safe state. As a result of the program implementation, groups of specialists with the necessary expertise in spent nuclear fuel (SNF) management technologies will be trained at NNC RK. Overall, this will contribute to strengthening the competitiveness of Kazakhstani science in the nuclear sector.
Program Objective
Rationale for the selection and implementation of the technology for solid radioactive waste treatment from the BN-350 reactor facility (RF).
Expected Outcomes
Direct results:
Scientific Direction No.1. “Evaluation of the amount of generated SRW at the BN-350 RF, their classification by type and activity”:
- Classification of SRW generated at the BN-350 RF by type, activity and volume was conducted;
- Methods have been developed for studying the physical and chemical properties of SRW, according to their classification;
- Results of a study of the physical and chemical properties of different types of SRW were obtained.
Scientific Direction No.2. “Development of proposals for the choice of SRW treating technology”:
- Basic requirements for the composition, structure and physical and mechanical properties of the matrix for immobilization have been determined;
- Methodology has been developed for obtaining candidate matrix compositions and testing them for compliance with established requirements.
Scientific Direction No.3. “Selection of a method for SRW immobilization generated at the BN-350 reactor”:
- Composition of the matrix for different types of SRW was determined;
- Recommendations were developed for optimizing the stages of SRW immobilization technology for the BN-350 reactor.
Final Outcome:
Scientific Direction No.1. “Evaluation of the amount of generated SRW at the BN-350 RF, their classification by type and activity”
A set of data will be obtained on the types, volume and physical and chemical properties of SRW from the BN-350 RF.
Scientific Direction No.2. “Development of proposals for the choice of SRW treating technology”:
Proposals will be developed to optimize the technology for immobilizing SRW from the BN-350 RF, taking into account their updated properties.
Scientific Direction No.3. “Selection of a method for SRW immobilization generated at the BN-350 reactor”:
Matrix compositions/compositions and recommendations for optimizing the technology for immobilization of SRW from the BN-350 RF will be determined.
The economic effect will be in obtaining our own technology for the immobilization of SRW generated as a result of the operation of a fast neutron reactor with a sodium coolant. Optimization of the existing SRW immobilization technology will be aimed at simplifying it, without losing the quality of the matrix, which will reduce the cost of the technological process.
The environmental effect consists of reducing the negative impact of RW on people and the environment by collecting information, classifying and developing matrices for reliable isolation of waste, taking into account the characteristics of the state of aggregation, radionuclide composition, physical-mechanical, chemical and biological properties.
Proposals for the concept of SRW managing generated at nuclear facilities in Kazakhstan will form the basis for the development of technical approaches to the immobilization, storage and disposal of waste.
The social effect is:
- Expanding the regulatory framework for the management of solid radioactive waste, in particular, to bring them into a conditionally safe state;
- Participation in international programs for RW management, increasing competencies in this area;
- Increasing the competitiveness of Kazakhstani science in the nuclear industry.
The area of outcome application is RW management, ensuring radiation safety of the population and the environment, training specialists for the nuclear industry.
As a result of the program implementation, the following will be achieved:
Publication of at least 6 articles and/or reviews in peer-reviewed scientific journals within the program’s research field, included in the 1st, 2nd, and/or 3rd quartile by impact factor in the Web of Science database and/or having a CiteScore percentile of at least 50 in the Scopus database. Publication of at least 7 (seven) articles in journals recommended by the CQASHE.
Publication of at least 1 (one) monograph or textbook in Kazakhstani publishing houses.
Obtaining at least 1 (one) patent from foreign patent offices (European, American, or Japanese) or at least 1 (one) foreign or international patent included in the Derwent Innovations Index (Web of Science, Clarivate Analytics), or at least 3 (three) intellectual property objects registered with the National Institute of Intellectual Property of the Republic of Kazakhstan.
Main Results of the Research Work
In 2024, the following results were obtained:
– Classification of solid waste generated at the BN-350 reactor facility by type, activity, and volume was completed,
– Characteristics of wastes to be included in the matrix (sludges, precipitates, ion-exchange resins, or irradiated material powders) were described in accordance with technical documentation,
– Information on solid waste generated at the BN-350 reactor facility was collected,
– Methodologies for studying the physicochemical properties of solid waste, according to their classification, were developed,
– A review of solid radioactive waste processing methods potentially applicable to the waste generated at the BN-350 reactor facility was carried out,
– Methodologies for studying the physicochemical properties of solid waste, according to their classification, were developed,
– Results of the physicochemical studies of different types of solid waste were obtained,
– Samples of different types of solid waste from the territory of the Mangistau Atomic Energy Complex were selected,
– Results of the physicochemical studies of various types of solid waste were obtained,
– Technical reports were prepared characterizing each type of waste at the BN-350 reactor facility.
In 2025, the following results were obtained:
– The main requirements for the composition, structure, and physicomechanical properties of matrices for waste immobilization were formulated,
– Proposals were developed for the methodology to obtain candidate matrix compositions and test them for compliance with the established requirements,
– A research and testing program was compiled for matrix compositions containing solid radioactive waste,
– A testing program was developed for selecting the component ratios of matrices for the immobilization of solid waste, based on the developed methodology,
– An R&D program was developed for testing matrix samples to ensure compliance with the requirements for composition, structure, and physicomechanical properties.
Expected results in 2026:
– Results of studies on matrices obtained under laboratory conditions will be obtained,
– Scientifically justified ratios of components for candidate matrices will be determined,
– Standard samples of candidate matrices will be created for testing,
– Results of matrix testing and verification of their compliance with the requirements for composition, structure, and physicomechanical properties will be obtained,
– Recommendations for optimizing the stages of the immobilization technology for solid waste from the BN-350 reactor will be formulated,
– Matrices demonstrating the highest compliance with established requirements will be selected,
– An assessment of the cost of raw materials for the matrices will be performed,
– An assessment of the cost of materials and equipment for implementing the immobilization stages will be performed,
– An optimal method for immobilizing solid waste will be proposed based on the obtained results.
Based on the results of the work in 2024–2025, the following were published:
Articles in journals indexed in the Scopus / Web of Science (WoS) databases:
1. Mukhamedov N.; Toleubekov K.; Vityuk G.; Bekmuldin M.; Dolzhikov S. Decommissioning of the BN-350 Fast Neutron Reactor: History Review and Current Status. Energies 2025, 18, 3486. https://doi.org/10.3390/en18133486
2. Mukhamedov N.; Baklanov V.; Moldagulov M.; Toleubekov K.; Surayev A.; Yagudin A.; Kanatnikov S. The BN-350 Reactor Decommissioning: Quantitative Analysis and Prospects for Solid Radioactive Waste Management. Energies 2025, 18, 4651. https://doi.org/10.3390/en18174651
Articles in journals recommended by the CQASHE:
1. Vityuk G.A., Mukhamedov N.Ye., Vityuk V.A., Irkimbekov R.A., Zhanbolatov O.M., Kuzdeubay A.A., Mukhamediyev A.K. Justification of the Safety of Spent Nuclear Fuel Transportation from the IVG.1M Reactor // NNC RK Bulletin, 2025, Issue 3(103), pp. 37–49. https://doi.org/10.52676/1729-7885-2025-3-37-49
2. Kabdylkakov Ye.A., Suraev A.S., Mukhamedov N.Ye., Dolzhikov S.A., Pakhnits A.V. Modeling of Ohmic Heating of the Electrode in the Electroslag Remelting Installation Using ANSYS // NNC RK Bulletin, 2025.– Issue 3(103).– pp.147-155. https://doi.org/10.52676/1729-7885-2025-3-147-155
3. Seken D.M., Surayev A.S., Mukhamedov N.Ye., Irkimbekov R.A., Zhanbolatov O.M. Calculation of Post-First-Fuel-Cycle Radionuclide Accumulation in the WWER-1000 Reactor Core // NNC RK Bulletin, 2025.– Issue. 4(104).– pp.119-126. https://doi.org/10.52676/1729-7885-2025-4-119-126
Patents
1. Patent of the Republic of Kazakhstan for a Utility Model No. 11611 – Protective damping casing for transportation and storage of ampoule-type irradiation devices / Mukhamedov N.Ye., Vityuk V.A., Pakhnits A.V., Surayev A.S., Vityuk G.A., Dolzhikov S.A., Bogomolova I.N., applicant and patent holder RSE NNC RK – No. 2025/1389.2; applied on 17.09.2025; published on 26.12.2025; Bulletin No. 52.
The results of the research were presented at the XI International Conference “Semipalatinsk Test Site: Heritage and Prospects for the Development of Scientific and Technical Potential”, held in Kurchatov from October 6 to 10, 2025, as well as at the XI International Conference “Current Problems of Nuclear Energy and Nuclear Technologies”, held in Tashkent, Uzbekistan, from October 14 to 16, 2025.