Relevance
One of the goals in the State policy of the Republic of Kazakhstan is to achieve the Carbon neutrality. Approved by the Decree of the President of the Republic of Kazakhstan Kassym-Jomart Tokayev The Strategy on Achieving Carbon Neutrality in the Republic of Kazakhstan by 2060 sets out that the nuclear power plants will be the part of the capacities’ structure as a stable source of energy. The sustained work has been led in this direction in order to make a vision for the development of nuclear energy, prepare decision on the construction of a nuclear power plant (NPP) as one of the main options for the development of carbon-free energy sources in the country. Such a decision will certainly be based on existing competencies, human resources and research results that create a scientific and technological basis for the development of the industry.
Program realization will ensure preserving and developing scientific, technical and intellectual potential for nuclear industry, creating technological basis for the development of nuclear energy and making new solutions to provide high-quality implementation of nuclear energy programs both in Kazakhstan and worldwide.
The program plans to cover research in the following directions:
The first research direction of the program will be focused on study of the processes being conducted at the reactor and non-reactor test benches with the aim to improve safety and efficiency of nuclear power that are important in choosing areas for the industry development and to create a basis for developing new solutions in order to ensure high performance of nuclear power programs in Kazakhstan and throughout the world.
Study results will be data on the processes and parameters of high-temperature interaction between the corium with structural materials and liquid metal coolant of power nuclear reactors as well as on transformation of structural-phase state of the products’ interaction over time. Possible application of lithium eutectic as functional materials of a thermonuclear reactor blanket has been justified. A method has been developed for an improved assessment of energy release in materials irradiated in the reactor over the entire operating range of its parameters.
The second research direction of the Program will cover research in the field of nuclear, radiation technologies and nuclear power materials promoting knowledge-intensive technologies addressing the urgent tasks of producing new advancing materials with improved properties, updating measuring methodologies and structural materials’ testing technologies.
The research will result in creation of new technology of testing the heat resistance of advanced structural materials by means of miniature samples, as well as the methods of instrumental testing. Data on the assessment of radiation damage to the long-term strength of materials and data on the content of activated micro-impurities in the components of local concretes are obtained. The regularities of the process of dissolution of nanoscale oxides in a steel powder matrix are revealed. Data on over-time transformation of corium structural-phase state with structural materials of power nuclear reactors are also obtained.
The third research direction of the Program will cover the study in the field of development and improvement of methods for assessing the impact of nuclear fuel cycle facilities on the environment and public health, allowing to form a true understanding of radio ecological situation and better understanding of possible mechanisms of the impact of hazardous factors on humans and the environment, as well as to develop solutions for their mitigation. Based on the results of the research, new methods will be developed for determining ultra-low concentrations of long-lived daughter products of Uranium-238 decay (U238) in environmental objects, methods for cleaning waters contaminated with man-made radionuclides, models for predicting the intensity of accumulation of radionuclides in agricultural plants, recommendations for the use of stable isotopes of water for monitoring water bodies in the zone of radionuclide pollution will be established.
And the fourth research direction of the Program will cover research to support nuclear events and radiation accidents monitoring development allowing to form the basis for creation and functioning of the existing system in Kazakhstan. The work results will be background levels of radionuclides in the main components of natural environment, dose load on the population and initial data for the creation of a radiation monitoring system on the territory of the expected construction of nuclear power plants, evaluation of the effectiveness of methods for bio indication of radioactive contamination of natural ecosystems, as well as improving the methodological level of biodosimetric methods for preparedness and response in emergency radiological/nuclear situations. Technologies for determining the geoelectric and elastic parameters of soils in the zones of influence of nuclear industry facilities and the construction of hodographs for weakly seismic regions of Kazakhstan based on unique archival records of peaceful nuclear explosions will be improved.
The vision for the development of fuel and energy complex in Kazakhstan in the coming years (Concept of the development of fuel and energy complex in Kazakhstan during 2023-2029) is closely associated with nuclear industry development and preparation of highly qualified human resources for nuclear energy.
The implementation of the Program will contribute to the solution of this task and achievement of the objectives and planned targets set out in Strategic Plan of Ministry of Energy of the Republic of Kazakhstan.
During the period of research work, the Program will allow to apply experimental methods using nuclear facilities and updated scientific equipment, engineering developments, information and analytical methods, radiological and geophysical monitoring techniques.
Research results will be published in peer-reviewed scientific logs, and applications of patents for invention will be submitted.
Program Objective:
Scientific and technical justification for sustainable and safe development of peaceful use of atomic energy, obtaining a complex of scientifically justified calculation-theoretic and experimental data necessary for nuclear power industry development in the Republic of Kazakhstan..
Expected Outcomes
Direct results:
On the research direction 01. Study to ensuring safety and efficiency of nuclear and thermonuclear energy:
On the research direction 02. Nuclear, radiation technologies and materials in nuclear power engineering:
On the research direction 03. Radiation and environmental safety of nuclear energy:
On the research direction 04. Development of monitoring system for nuclear events and radiation accidents:
Final Result:
- In 2024, as part of the program implementation, computational studies were conducted to justify large-scale experiments on physical modeling of a severe accident with core melting in a light-water reactor, determining key parameters such as the dimensions of the experimental section, the amount of prototypical corium to be produced, methods for simulating residual heat release (heater type, power, and duration), and experimental conditions; results of calculations justifying experimental studies of corium fragmentation in sodium coolant were obtained, and an experimental program was prepared; neutron-physical and thermophysical calculations were performed to justify the feasibility of in-reactor experiments at the limiting operating parameters of the IGR reactor; the upgraded TiGrA test bench was modernized and optimal parameters for experiments with lead-lithium eutectic under thermal loads were determined; a ready instrumental base was established for creep testing using miniature specimens (Small Punch Creep); structural features of the obtained powder compositions (crystal structure, crystallite size, phase composition, particle size, etc.) were characterized depending on high-energy processing regimes; literature data on neutron activation regimes of impurities in materials were reviewed, irradiation regimes were calculated, and other justifications were prepared for experiments on the IVG.1M reactor, including a prepared experimental program and samples of concrete and structural materials from major domestic manufacturers; corium samples obtained from experiments simulating severe accidents in VVR reactors were systematized according to initial corium composition, accident progression conditions (in-vessel and ex-vessel), and final characteristics (granulometric, phase, and elemental composition), enabling comparable corium samples for further research; technological schemes were developed for laboratory experiments in the preparation of counting samples for alpha-spectrometry, gamma-spectrometry, and liquid scintillation alpha-beta spectrometry; quantitative patterns of radionuclide accumulation in agricultural plants were established as input parameters for models; methodological approaches were developed for preparing experimental soil extract samples for radiochemical determination of transuranic radionuclides to study their mobility and bioavailability; studies were conducted on water purification from technogenic radionuclides using sorption methods, with quantitative efficiency indicators obtained; baseline values of stable isotopes ²H/¹⁸O in atmospheric precipitation, surface, and groundwater at radiation-hazardous sites were established, seasonal variations in ²H/¹⁸O content were identified, and deviation coefficients from the meteoric water line were determined; the formation of a monitoring well network for groundwater at the Granitny site was initiated, geological cross-sections were constructed based on previously obtained data, and the computer database on hydrogeological environment studies at the site was updated; research sites and objects were identified, contamination levels were established, and quantitative data on radionuclide content in natural ecosystem components (soil-vegetation cover, atmosphere, water bodies) were obtained; specific features of radionuclide accumulation by individual representatives of living ground cover and their separate organs were revealed, and data on the influence of ionizing radiation on plant biological characteristics were acquired; an adapted concept for action planning and internationally accepted algorithms for dose assessment in large-scale emergency radiation/nuclear situations were developed; results of the analysis of informativeness and reliability of available monitoring data on fracture zones, soil moisture, groundwater levels, geodynamic and hydrodynamic activity at nuclear industry facilities under technogenic electrical interference conditions were obtained; geoelectric parameters of various soils were determined based on physical modeling data; correlation relationships between geophysical parameters and soil water-physical properties were established; field research materials using a complex of geophysical methods were collected at the VVR-K INP (Institute of Nuclear Physics) site and the Kaskelen geophysical test site; seismic bulletins of peaceful nuclear explosions were prepared, refined parameters of peaceful nuclear explosions were obtained, and a database of digitized seismograms of peaceful nuclear explosions on the territory of Kazakhstan was created; results of monitoring observations were obtained with an assessment of geophysical monitoring technology using previously manufactured geophysical instrumentation.
- In 2025, experimental data were obtained on the behavior of candidate materials during their interaction with corium under conditions modeling a severe accident with core melting in a light-water reactor; experimental results were acquired on the interaction of a fast reactor core melt jet with sodium coolant; a technical design of an in-reactor experimental device was developed along with a prepared program of irradiation experiments on the IGR reactor in the “Regulated Pulse” mode, including the experimental device itself; prototype samples of lithium eutectics were produced, with results of microstructural, X-ray phase, and energy-dispersive analyses of the fabricated alloys; creep and long-term strength parameters of miniature specimens of austenitic steel were determined; studies were conducted on the specific features of structural-phase transformations in dispersion-strengthened (DSO) structural steel depending on spark plasma sintering conditions; a reactor experiment with standard specimens was performed to develop a methodology, an instrumental neutron activation analysis (NAA) method for the elemental composition of concrete was elaborated, and the contents of elements contributing significantly to the radiation environment in premises during NPP and thermonuclear reactor (TR) operation and decommissioning were determined; data on the properties of corium (structure, phase composition, elemental composition, microhardness) of identical compositions at different aging stages (from 5 to 20 years) under natural aging conditions were obtained; working instructions were prepared for the preparation of counting samples for ²²⁶Ra and ²¹⁰Pb measurements using alpha-spectrometry, gamma-spectrometry, and liquid scintillation alpha-beta spectrometry; models enabling prediction of radionuclide accumulation intensity in agricultural plants were developed; quantitative data on the mobility and bioavailability parameters of transuranic radionuclides in soils under various conditions of radioactive contamination formation were obtained; studies on water purification from technogenic radionuclides using filtration methods were conducted, with quantitative efficiency indicators and influencing factors determined; sources of formation of groundwater and surface water at various sites were identified, the degree of influence of atmospheric precipitation on the state of water bodies was assessed, data on water exchange processes between different aquifers and water bodies, as well as their rates and durations, were obtained; new information on the hydrology of surface waters at the site was acquired, including the location and volume of water masses, temporal variability in flow, and the impact of weather and climatic changes (precipitation and temperature), along with new data and information on the hydrogeochemistry of the site essential for safety assessment and repository design, new data on the geotechnical characteristics of rock and the chemical composition of groundwater at the site, and the computer database was updated to construct a hydroisohypse map of the site indicating the direction of groundwater flow; quantitative data on radionuclide content characterizing the radiation situation in populated areas (radionuclide content in the atmosphere, water supply facilities, and agricultural products) were obtained, and accumulation coefficients were calculated; specific features of radionuclide accumulation by individual representatives of living ground cover, as well as invertebrates and small vertebrates, were revealed; results of morphometric, morpho-anatomical, and cytogenetic studies of selected plant species at sites of radioactive contamination were obtained; operational solutions for timely assessment of individual absorbed dose under various irradiation scenarios were elaborated; field observation materials using a complex of geophysical methods at nuclear industry facilities were obtained, technologies for determining geoelectric and elastic parameters of soils in natural occurrence were improved, as well as monitoring and processing of spatiotemporal changes in geoelectric, elastic parameters, and gas permeability of the studied sections under technogenic electrical interference conditions and weakly manifested deformation processes, and results of method-by-method analysis of the informativeness and reliability of geophysical monitoring data were acquired; seismic bulletins of nuclear explosions and earthquakes from the Semipalatinsk Test Site (STS) area were prepared, parameters of nuclear explosions and earthquakes from the STS area were refined, and a database of digitized seismograms of peaceful nuclear explosions from the Caspian Depression, Uzbekistan, and Turkmenistan was created; a technical specification for the development of an experimental prototype of the measuring complex was prepared, results of mock-up testing of individual units and experimental studies to refine possible values of certain parameters of the designed measuring complex were obtained, and principal schemes were developed.
.
- In 2026, results of materials science studies on candidate materials (structure, erosion depth) were obtained, and recommendations were developed for the application of the investigated material as a protective layer in corium traps; experimental results were acquired on the investigation of fast reactor core melt jet interaction with sodium coolant; a technical design of an in-reactor experimental device was developed along with a prepared program of irradiation experiments on the IGR reactor in the “Regulated Pulse” mode, including the experimental device itself; prototype samples of lithium eutectics were produced, with results of microstructural, X-ray phase, and energy-dispersive analyses of the fabricated alloys; creep and long-term strength parameters of miniature specimens of austenitic steel were determined; studies were conducted on the specific features of structural-phase transformations in dispersion-strengthened (DSO) structural steel depending on spark plasma sintering conditions; a reactor experiment with standard specimens was performed to develop a methodology, an instrumental neutron activation analysis (INAA) method for the elemental composition of concrete was elaborated, and the contents of elements contributing significantly to the radiation environment in premises during NPP and thermonuclear reactor operation and decommissioning were determined; data on the properties of corium (structure, phase composition, elemental composition, microhardness) of identical compositions at different aging stages (from 5 to 20 years) under natural aging conditions were obtained; working instructions were prepared for the preparation of counting samples for ²²⁶Ra and ²¹⁰Pb measurements using alpha-spectrometry, gamma-spectrometry, and liquid scintillation alpha-beta spectrometry; models enabling prediction of radionuclide accumulation intensity in agricultural plants were developed; quantitative data on the mobility and bioavailability parameters of transuranic radionuclides in soils under various conditions of radioactive contamination formation were obtained; studies on water purification from technogenic radionuclides using filtration methods were conducted, with quantitative efficiency indicators and influencing factors determined; sources of formation of groundwater and surface water at various sites were identified, the degree of influence of atmospheric precipitation on the state of water bodies was assessed, data on water exchange processes between different aquifers and water bodies, as well as their rates and durations, were obtained; new information on the hydrology of surface waters at the site was acquired, including the location and volume of water masses, temporal variability in flow, and the impact of weather and climatic changes (precipitation and temperature), along with new data and information on the hydro geochemistry of the site essential for safety assessment and repository design, new data on the geotechnical characteristics of rock and the chemical composition of groundwater at the site, and the computer database was updated to construct a hydroisohypse map of the site indicating the direction of groundwater flow; quantitative data on radionuclide content characterizing the radiation situation in populated areas (radionuclide content in the atmosphere, water supply facilities, and agricultural products) were obtained, and accumulation coefficients were calculated; specific features of radionuclide accumulation by individual representatives of living ground cover, as well as invertebrates and small vertebrates, were revealed; results of morphometric, morpho-anatomical, and cytogenetic studies of selected plant species at sites of radioactive contamination were obtained; operational solutions for timely assessment of individual absorbed dose under various irradiation scenarios were elaborated; field observation materials using a complex of geophysical methods at nuclear industry facilities were obtained, technologies for determining geoelectric and elastic parameters of soils in natural occurrence were improved, as well as monitoring and processing of spatiotemporal changes in geoelectric, elastic parameters, and gas permeability of the studied sections under technogenic electrical interference conditions and weakly manifested deformation processes, and results of method-by-method analysis of the informativeness and reliability of geophysical monitoring data were acquired; seismic bulletins of nuclear explosions and earthquakes from the Semipalatinsk Test Site (STS) area were prepared, parameters of nuclear explosions and earthquakes from the STS area were refined, and a database of digitized seismograms of peaceful nuclear explosions from the Caspian Depression, Uzbekistan, and Turkmenistan was created; a technical specification for the development of an experimental prototype of the measuring complex was prepared, results of mock-up testing of individual units and experimental studies to refine possible values of certain parameters of the designed measuring complex were obtained, and principal schemes were developed.
Over the course of the entire program, publications will be prepared and published:
– no less than 4 (four) articles and/or reviews in peer-reviewed scientific editions in scientific area of the program included in the 1-st, 2-nd or 3-rd quartiles in the Web of Science and (or) having at least 40 Cite Score percentile in Scopus;
– or at least 3 (three) articles and/or reviews in peer-reviewed scientific editions included in 1-st, 2-nd or 3rd quartiles in Web of Science and(or) having at least 40 Cite Score percentile in Scopus, and at least 1 foreign or international patent included in Derwent Innovation Index Clarivate Analytics;
– and at least 5 (five) articles in a peer-reviewed foreign and (or) domestic journals with non-zero impact factor (recommended by Committee for Provision Control in the Sphere of Science and Higher Education),
R&D Main Results
In 2024, as part of the Implementation of the Program “Developing of Nuclear Power Engineering in the Republic of Kazakhstan” the following key results were achieved:
Section 01 ‘Research to improve the safety and efficiency of nuclear and thermonuclear energy’:
1) Computational studies in support of large-scale experiments on physical modeling of a severe accident with meltdown of the core of a light-water reactor have been conducted. Calculations of the thermal state using the ANSYS program confirmed consistency with experimental data, which allows using the developed thermal-physical model for further planning of experiments. The ED scheme has been selected and the optimal method for simulating decay energy has been determined. Induction heating has been recognized as preferable for maintaining the corium in a molten state due to its ability to provide a uniform thermal field, which brings the experimental conditions as close as possible to real emergency processes. These results serve as a basis for further large-scale studies at the LAVA-B facility.
2) A calculation and theoretical justification for the experimental work on studying the fragmentation length of the corium of a fast reactor with sodium coolant at the EAGLE test-bench has been performed. As part of the preparation for the experiment, an ED has been designed, the design of which includes upper and lower melt traps and ensures effective control of the melt movement through the drain pipe. Calculations of the thermophysical model of the EMF crucible for induction heating have been performed using the ANSYS program, which made it possible to verify the calculated temperature values based on the FDCO-7 experiment data. Comparison of the calculated and experimental data showed a sufficient degree of consistency with deviations within 9-19%.
3) The IMPULSE ED has been developed to study the maximum operating modes of the IGR reactor. Neutronic and thermal-hydraulic calculations have confirmed the possibility of safely conducting experiments with the fuel of the power reactor. The maximum temperature of the fuel element was 981 K at a power of 3 kW, and the steady-state heat exchange mode was achieved in 50 seconds. The obtained results allow us to proceed to the development of a test program and further reactor experiments to study the maximum capabilities of the IGR reactor in the ‘Controlled Pulse’ mode.
4) The Tigray experimental stand has been successfully upgraded to study the interaction of lithium eutectic alloys with chemically active gases under thermal loads. A system for feeding gas and steam-gas mixtures was integrated into the stand, which made it possible to implement various experimental modes. A methodology for conducting experiments, including procedures for preparing samples and analyzing their interaction with gas mixtures, was developed and successfully tested. A series of experiments with various gas and steam-gas mixtures was conducted, which confirmed the operability of the developed methodology. The main methodological parameters were determined, including temperature conditions, heating rates and gas concentrations required for further research on the TiGrA stand.
Section 02 ‘Nuclear, radiation technologies and materials in nuclear power’:
1) The equipment base for creep testing using small samples has been prepared. A basic diagram of the testing machine units connection has been developed and implemented, and the necessary auxiliary equipment and materials for the testing unit have been selected. As a result of upgrading the HT-1500-S-CR testing machine IMS, it has been possible to increase the control accuracy and information content of data during long-term testing, which will ensure reliable results when testing materials under high loads and temperatures. The commissioning has confirmed the readiness of the unit for operation.
2) Studies have been conducted on the synthesis of composite powders of ODS steels by mechanochemical processing. The main results have shown that the use of stearic acid as an additive during mechanosynthesis significantly affects the morphology and structure of the powders. Optimum results were achieved with the addition of 3-5% stearic acid, which ensured the production of particles with improved compactability and high dispersion. Mechanosynthesis parameters, such as acceleration of 350 rpm and a processing time of 8 hours, demonstrated the greatest efficiency in achieving a uniform distribution of oxides in the material matrix and preventing particle agglomeration. The data obtained will be used for further development of the technological process for creating ODS steel samples.
3) Preparations has been performed to develop a methodology for instrumental NAA of the elemental composition of concrete and structural materials. A literature review has shown the importance of choosing low-activation concrete compositions to reduce the volume of radioactive waste during decommissioning of NPPs. Based on neutronic and thermophysical calculations of the parameters of the ED at the IVG.1M reactor, the conditions for conducting NAA experiments were determined. The results of energy release calculations showed that concrete samples demonstrate a maximum specific energy release of 0.13 W/g, and thermophysical calculations confirmed that with a reactor power of 300 kW, the maximum temperature of the samples will not exceed 41°C. The main provisions of the experiment program have been developed.
4) A number of model compositions of corium were selected for further study of changing its structural and phase state. An analysis of data on various types of corium used in experiments over the past 30 years was performed, and the parameters of the experiments and characteristics of corium were systematized. As a result, a database was developed that allows comparing various parameters of corium and experimental conditions. The analysis of existing methods for studying the aging processes of corium showed that the key factors influencing the change in its properties are density, porosity, mechanical characteristics, elemental and phase composition, as well as leaching during aging. These data will form the basis for further research and development of methods for predicting the behavior of corium during long-term storage and transportation, as well as when handling it in emergency conditions.
Section 03 ‘Radiation and environmental safety of nuclear energy’:
1) Flow cahrts for conducting laboratory tests in the field of preparation of counting samples for the spectrometric determination of 226Ra and 210Pb have been determined. Experiments on the separation and isolation of elements using deposition and ion exchange methods have been carried out. During the deposition of hydroxides, the bulk of alkaline and alkaline earth elements is in the filtrate. The amount of alkaline and alkaline earth elements released as a result of the redeposition of hydroxides ranged from 5 to 30%. Experiments using strongly basic anion-exchange resin 17×8 in Cl-form have shown that, along with alkaline and alkaline earth elements, elements such as Cu, Ni, Co are isolated in the eluate, which indicates the absence of absorption of these elements by anion exchange resin. Upon deposition of barium sulfate, the bulk of Na, Mg, K, Cs, Ca, Cu, Co, Ni, Zn, Cd can be isolated into the filtrate.
2) It was found that the accumulation of 137Cs by agricultural plants is associated with its bioavailability in the soil (r=1, p<0.05), which, in turn, is determined by the mechanisms of formation of radioactive contamination and certain soil physico-chemical parameters. The intensity of absorption of bioavailable 137Cs by plants and, as a result, the accumulation of radionuclide in crop production primarily depends on the gross K content in the soil (rxy-z = -0.85; p<0.05). It has also been established that the absorption of strongly bound forms of 3H from the soil by agricultural plants is indirect and species-specific. It is assumed that the key role in the absorption of strongly bound forms of 3H belongs to the processes of physico-chemical and biochemical leaching. The results obtained are input parameters for identifying patterns of migration and accumulation of 137Cs and 3H in the ‘soil-agricultural plants’ system and development models to predict the intensity of accumulation of radionuclides in crop production.
3) Experimental data characterizing the bioavailability of 241Am in the soil and vegetation cover of two radioactively contaminated plots of the STS were obtained. The values of the concentration factor (TF) for plants at the plot in the area of the ‘P-3’ site vary in the range from 0.00013 to 0.0045, at the plot in the area of the ‘P-2M’ site – in the range from 0.0028 to 0.0226. Methodological techniques for the preparation of alkaline soil extracts for the radiochemical determination of 239+240Pu have been developed.
4) Experimental studies of sorption and desorption processes with one type of sorbent were carried out, during which quantitative indicators of the effectiveness of the sorption method were obtained – the percentages of sorption and desorption for 137Cs and 90Sr. It was found that for one type of water, the sorption percentage for 137Cs is higher than for 90Sr. The factors influencing the sorption processes are determined: the size of the sorbent particles, the contact time of the sorbent and the purified water, the chemical composition of the water. It was found that for a sorbent with a smaller particle size, the percentage of sorption is higher than for a sorbent with a larger particle size. It was also found that with an increase in the contact time of the sorbent and the purified water, the percentage of sorption increases. The chemical composition of the purified water also affects the sorption processes, with an increase in water mineralization (the amount of substances dissolved in water), the sorption efficiency decreases. Accordingly, to increase efficiency, it is necessary either to increase the mass of the sorbent or to reduce the volume of purified water. Based on the conducted experiments, methodological recommendations for the purification of contaminated waters by the sorption method have been developed.
5) Initial values of stable isotopes 2H and 18O in atmospheric fallout were obtained, and a local line of meteoric waters was constructed. The coefficient of deviation of the local from the global line of meteor waters is calculated. According to the results of studies of the waters of radiation-hazardous objects of the ‘Telkem’ and ‘Degelen’ sites, it was revealed that there is no water exchange between ground water and surface waters at the ‘Telkem’ site area. The ground water of ‘Telkem’ site differs significantly from surface waters in the light isotope values. It has been established that all the waters of creeks and springs studied at the ‘Degelen’ site are fed from ‘combat’ adits with water manifestations. The exception is the waters in the northeastern and eastern parts of the ‘Degelen’ site, located in the area of the Karabulak r., which, like the waters of the Karabulak r. itself, differ in isotopic composition and have a separate fed source.
6) The studies conducted by a number of drilling works, geophysical methods (logging), hydrogeological works and laboratory methods made it possible to expand the monitoring network and obtain new information on the crystalline rock block and hydrogeological conditions at the Granitniy site as a potential RAW disposal site. At the Granitniy site, based on the results of previous drilling activities, to expand the monitoring network and study the crystalline rock massif, an analysis was conducted that resulted in the construction of two geologic cross sections that allowed for a more visual representation of the location of the crystalline rock massif at the Granitniy site. As a result of hydrogeological monitoring and hydrochemical analyses, new groundwater data was obtained at the Kosshoky, Akbota-Zapadny and Granitniy sites. Based on the results of the work, graphs of groundwater levels for the last six years and maps of hydroisohyps for the three sites were constructed.
Section 04 ‘Development of nuclear events and radiation accidents monitoring system’:
1) The sites and objects of research have been identified – the main components of the steppe terrestrial ecosystem, as well as the aquatic ecosystem of the Irtysh r. in the area of the Kurchatov t., Abai region. Contamination levels have been established: the content of radionuclides in the topsoil (0-5 cm) is from 130 to 1470 Bq/kg for 40K, 232Th – from 6 to 70 Bq/kg, 238U – from < 5 to 150 Bq/kg, 137Cs – from < 0.1 to 65 Bq/kg, 210Pb – from < 3 to 175 Bq/kg, 241Am – from < 0.1 to 24 Bq/kg; in vegetation: 40K – from 6 to 670 Bq/kg, 232Th – from < 0.4 to 10 Bq/kg, 137Cs – from < 0.2 to 28 Bq/kg, 210Pb – from < 0.5 to 25 Bq/kg, 3H (organically bound) from 6×10-3 to 3.1 Bq/kg; in surface and ground waters: 3H – from < 6 to 22±6 Bq/kg, 137Cs – from < 0.01 to 4.3±1.7 Bq/kg, 90Sr – from < 0.01 to 2±0.02 Bq/kg, 239+240Pu – from < 1.1×10-4 to (1.1±0.8)×10-3 Bq/kg; the presence of 241Am, 137Cs, 90Sr in atmospheric air has not been recorded, the numerical values of 239+240Pu range from 3.0·10-9 to 6.0·10-7 Bq/m3. Methodological recommendations have been developed to assess the radiation dose exposure on the population in the zone of influence of NPP.
2) The features of the accumulation of radionuclides by individual representatives of the living ground cover and their individual organs were revealed – a series of decreasing the Tf of 241Am for meadowsweet (Spiraéa hypericifólia): roots > stems > leaves > blooms. At the same time, the Tf of 241Am for roots is two orders of magnitude higher than for other organs. To study the effect of H3 on the morpho-anatomical parameters of the pinto bean (Phaseolus vulgaris), a model experiment was started on 6 hydroponic installations under laboratory conditions. Cytogenetic changes of fescue grass (Festuca valesiaca Gaudin) growing in conditions of radioactive contamination have been established, which shows the possibility of using this species for bioindication of habitat quality and its individual indicators in conditions of radioactive contamination of terrestrial ecosystems.
3) Based on the guidelines of the IAEA, WHO, and the International Organization for Standardization, the concept of action planning and sustainable international algorithms for biodosimetric radiation dose assessment for sorting in large-scale emergency radiation/nuclear situations have been studied and adapted. The operational key large facilities in Kazakhstan – potential sources of radiation hazard in the event of incidents and emergency radiation/nuclear situations have been studied. As part of the research and preparation for possible radiation incidents, the potential RRF Baikal-1, located 65 km from the Kurchatov t., was selected as a model for considering an emergency situation. A study of the background frequency of unstable chromosomal aberrations – the zero dose point in 27 employees of this facility has been initiated.
4) An analysis of the informativeness and reliability of hydrodynamic and geodynamic monitoring data for aquifers using the induced polarization (IP) method in dipole and vertical electrical sounding (VES) modifications has been conducted. Methods for suppressing technogenic electrical interference were tested by optimizing observation systems, calculating the differential phase parameter, and evaluating the percentage-frequency effect. The effectiveness of the combined use of seismic exploration methods – correlation method of refracted waves (CMRW) and electrical exploration methods – vertical electrical sounding (VES), to improve the reliability of interpreting conductive horizons as being associated with the presence of groundwater was confirmed using data from the ‘Kaskelen’ geophysical testing site. Geoelectric parameters of sandy-clay soils were obtained as a function of moisture content based on physical modeling data, and correlation relationships between these parameters were determined.
5) Information on peaceful nuclear explosions in the territory of the former USSR, including the territory of Central Asia, was collected. The result of the work was the database ‘Metadata’. The database was created in two versions (Excel and CSS 3.0) and includes 107 peaceful explosions for 233 stations. The parameters for a number of peaceful explosions have been refined, concerning location refinement, additional determination of magnitudes and energy classes, in total 21 explosions (coordinates) and 81 explosions (magnitudes, classes) have been refined. A seismic bulletin was compiled, incorporating all refined source data for explosions, as well as characteristics determined from the processing of paper seismograms – regional seismic wave arrival times, amplitudes, and periods.
6) Work was carried out to justify the parameters of the designed measurement complex and the technology of geophysical monitoring under conditions of technogenic interference based on monitoring observations obtained using previously developed geophysical equipment. The results of the analysis of scientific and technical information made it possible to determine the main electrical parameters of the designed measurement complex: minimum detectable signal (no more than 0.02 μV); industrial frequency noise suppression (at least 100 dB); resolution (at least 32 bits); amplitude measurement error (no more than 0.2%); phase parameter measurement error (no more than 0.01 degrees). These parameters are comparable to the best international counterparts.
The reliability of the results and conclusions obtained within the framework of the research is ensured by a representative volume of analyzed literature data and a comprehensive review of global experience on the studied topics; the application of well-established research methodologies and approved and certified techniques; the use of mathematically substantiated computational methods and licensed software in theoretical and computational studies; the application of verified and calibrated instrumental and analytical equipment in experimental work, modern methods of statistical data processing, and the consistency of these data with the results of theoretical and computational studies, among other factors.
The research team of this program includes: 1 Doctor of Science, 8 Associate Professors, 3 Candidates of Science, 18 PhD, 15 postgraduate and doctoral students, 47 masters, 7 master’s students. The number of young scientists and specialists (under 35 years old) is 96.
Based on the results of the research, 13 publications were prepared, including 8 articles. The main findings were presented at international conferences: the V International Scientific Forum "Nuclear Science and Technology", the 8th Nuclear Materials Conference (NuMat 2024).
In 2025, as part of the Implementation of the Program “Developing of Nuclear Power Engineering in the Republic of Kazakhstan” the following key results were achieved:
Regarding Section 01, “Research on Enhancing the Safety and Efficiency of Nuclear and Thermonuclear Energy”:
1) Data have been obtained on the behavior of candidate materials when interacting with cladding under conditions simulating a severe accident in a light-water reactor involving core melting. It has been established that cladding causes cracking, erosion, and partial destruction of aluminum oxide blocks. Information on the nature and extent of structural changes, as well as the depth of erosion of the candidate material as a result of interaction with the cladding, will be obtained after a comprehensive set of materials science studies planned for next year.
2) Design and software-methodological documentation have been developed, all elements of the ED have been manufactured, and the ED assembly was carried out on the EAGLE test bench. Experimental results were obtained on the interaction of the fast reactor core melt jet with the sodium coolant. Diagrams showing changes in power in the EMF and temperature values from thermocouples installed in the ED were constructed. Analysis of the obtained results and post-experimental studies of the samples are planned for 2026.
3) Technical design of the ED has been completed, and software-methodological documentation developed, including the irradiation experiment program on the IGR reactor operating in “Controlled Pulse” mode. Safety justification for conducting in-reactor experiments in “Controlled Pulse” mode using power reactor fuel at the limiting operational parameters of the IGR was carried out. Additionally, assembly and preparation of the IMPULSE ED for experiments have been completed.
4) An experimental unit was developed, manufactured, and assembled for the synthesis of low-melting eutectic lithium alloys based on lead and tin. Technological procedures for synthesizing lithium alloys with lead and tin were selected and refined. A synthesis program was developed, resulting in experimental alloy samples with specified atomic ratios of metals. Characterization of the produced samples was carried out using differential scanning calorimetry, microstructural analysis, and X-ray phase analysis. The specific heat capacity of the lead-lithium eutectic was determined. The alloy was found to have a homogeneous structure and a phase composition corresponding to Pb₈₄Li₁₆. The melting point of the eutectic is approximately 233.4 °C, with a specific enthalpy of fusion of 21.5 J/g. The heat capacity during melting is 247 J/g·°C, and during solidification is 242 J/g°C. The temperature dependence of specific heat capacity was determined in the range of 50 °C to 500 °C. The results of materials research confirmed the effectiveness of the lithium eutectic alloy synthesis method based on lead and tin and demonstrated its suitability for producing samples.
Section 02: Nuclear and Radiation Technologies and Materials in Nuclear Power Engineering
1) Methodical long-term tests were carried out on samples of austenitic steel grade 12Х18Н10T. The time to failure and the average creep rate in the linear section were determined under specified test conditions. The time to failure at a test temperature of 700 °C was 31.8 hours, while at 800 °C it was only 0.5 hours. This demonstrates the exponential sensitivity of steel creep to temperature increase, which is typical for austenitic stainless alloys. The average punch displacement rate in the linear portion of the curve was 0.0022 mm/h at 700 °C and 0.25 mm/h at 800 °C. The sharp increase in rate with temperature indicates the dominance of thermally activated creep mechanisms. The resulting creep curves clearly show all three stages: primary (decelerating) deformation, steady-state creep, and tertiary (accelerating) failure. The obtained data can be used to verify strength and durability parameters of structural materials operating under high-temperature conditions, including in next-generation power systems.
2) As a result of the conducted studies, it was established that the parameters of the SPS (Spark Plasma Sintering) significantly influence the microstructure and phase composition of ODS (Oxide Dispersion Strengthened) steel, and some specific features of the structural-phase transformation of structural ODS steel depending on the SPS conditions were identified. At temperatures below 1100 °C, incomplete densification is observed. At temperatures above 1400 °C, grain growth and degradation of the dispersed phase begin. Microstructural investigations showed that with increasing temperature, a more uniform and dense structure forms. At temperatures exceeding 1400 °C, recrystallization processes are activated, leading to grain coarsening and loss of structural homogeneity. According to X-ray phase analysis, the main phase in all samples is α-Fe (BCC), with alloying elements dissolved in the solid solution. Samples sintered at 1400 °C showed the highest content of Y₂O₃ (up to 30%) and the lowest amount of lattice defects. At 1500 °C, a decrease in Y₂O₃ content to 2.8% and an increase in Fe₃O₄ content were observed, indicating thermal instability. The key factor for preserving the strengthening oxide phase Y₂O₃ and maintaining a uniform structure is strict control of the temperature regime, in particular, limiting the sintering temperature to no higher than 1400 °C. Based on the results obtained, a methodology for producing steel using SPS technology was developed.
3) A set of experimental and methodological activities has been implemented aimed at the development and application of INAA for the quantitative determination of the elemental composition of concrete and similar materials. The work covered two research reactors, IVG.1M and IGR, and included the design of irradiation devices, calculations of nuclear-physical parameters, irradiation experiments, and gamma-spectrometric measurements. As a result of the work performed, an INAA methodology adapted to the conditions of the IGR reactor was developed. Detailed data on detection limits were obtained for a wide range of elements, including rare earth and transition metals. Detection limits for elements such as Eu, Sm, Sc, Tb, Lu, Hf, Ta, Co, Np, Ho, and others demonstrated high sensitivity of the method under the chosen irradiation and decay conditions. This confirms the feasibility of using INAA for analyzing elements at low concentrations, including actinides and rare earth metals. The methodology was validated on samples of rock standards SGD-2a and SG-4.
4) An analysis was conducted on the existing corium obtained from experimental studies of corium simulant retention processes using passive safety systems (such as the reactor vessel lower head, melt traps, and refractory materials) covering the period from 1997 to 2020. For further investigation of the natural aging process of corium, representative portions of samples of different ages were selected, ensuring similarity in composition and experimental conditions. The examined samples included both large fragments and powders. Fractionation of powdered samples was performed, followed by elemental and phase analyses for each fraction of every corium type, as well as an evaluation of corium storage conditions. A comparison of the current results with the original charge composition (components used to produce the WWR corium simulant) and an analysis of the experimental conditions (taking into account materials present in the melt trap) revealed a strong correlation with data collected at the time of the experiments. This indicates that under dry, long-term storage, corium does not undergo significant structural or phase changes.
Section 03 ‘Radiation and environmental safety of nuclear energy’:
1) The main stages of spectrometric sample preparation tried out. Research into the release of radionuclides and elements during deposition and ion exchange operations conducted. The concentration of Ba2+ isotopes is estimated to be sufficient for visual observation over precipitating BaC2O4. When adding 300 micrograms of Ba2+ as a carrier to the analyte, visual recording of precipitating BaSO4 failed. It was found that the use of iron compounds for the coprecipitation of Pb isotopes in the form of hydroxides at the final stages of purification is highly unadvisable, because the yellow or brown color of iron salts after dissolution of the Fe(OH)3 precipitate strongly affects the quenching of the spectrometric source, which in turn entails a decrease in sensitivity and distortion of the analysis results. Operating instructions have been prepared.
2) Simulation experiments with crops were conducted to evaluate the incorporation of 3H, as well as to obtain the parameters of the transfer of 243Am to corp prodcuts. Models have been developed to predict the accumulation rate of 3H in agricultural plants based on the concentration of TFW during the root and foliar uptake of HTO. As a result, it was found that individual models based on the concentration of free 3H in leaves are the most predictive. Such models are able to predict more than 60% of OBT concentration in leaves, both during the root and foliar uptake of 3H. The models developed from the generalized concentrations of 3H in the free water of leaves or the aerial parts of plants are either not statistically reliable, or are characterized by low predictive ability owing to a high heterogeneity of source data.
3) Figures were obtained on the mobility and bioavailability parameters of transuranic radionuclides in the land cover of the fallout plumes after gound tests at the Experimental Field. The values of Tf of 241Am for plants growing in the fallout plumes vary from 0.00003 to 0.023, those of 239+240Pu – from 0.00001 to 0.030. The maximum variability of 239+240Pu Tf is noted in the plume of the P-2M (II) (p. 14-16), where 241Am Tf, on the contrary, exhibits the shortest spread in values. The distribution pattern of 241Am AC values in mobile and acid-soluble forms in the soil of the fallout plumes is different. Based on the distribution of 241Am AC values and 241Am Ef in the soil of the P-3 plume, the coarse fractions tend to be sequentially enriched with 241Am as the distance from the ground zero increases.
4) Experimental studies have been conducted on the purification of contaminated waters from man-made radionuclides by membrane filtration the case of the STS water bodies, which differ in the formaiton mechanism of radioactive contamination and location. The purification efficiency in the study waters with respect to 137Cs was 100%, 239+240Pu – 98% for the water of the Telkem-1 crater and 100% for the water of the V-1 crater. It was found that the membrane filtration method is ineffective with respect to 90Sr, since this radionuclide is mainly in a dissolved form in the water. 137Cs in the water from a water stream of crater 609 and V-1 is in the form of a coarse suspension (>8), in the water of the Telkem-1 crater - 93% of this radionuclide is in a coarse suspension and 7% is distributed as suspended substances. The predominant speciation of 239+240Pu in the water of the V-1 crater is a coarse suspension; in the water of the Telkem-1 crater, this radionuclide is distributed in the form of coarse and suspended substances, as well as in the form of colloids of various size (up to 2%). Guidelines have been developed based on the experiments condcuted.
5) The sources of origin, water exchange processes, and conditions forming radionuclide-contaminated ground and surface waters have been identified for various radiation-hazardous sites at the STS marked by by different hydrogeological and environmental conditions. It was found that the main source of ground water recharge at the Balapan site is the infiltration of precipitation, river and meltwater. According to isotope analysis data, the replenishment pattern of water reserves at the Sary-Uzen site is pronounced seasonal due to snowmelt and spring precipitation. The distribution results of 3H in the surface and ground waters of the Uzynbulak, Baytles and Toktakushuk creeks at the Degelen site reflect differences in the mechanisms of water exchange. The consistency of concentrations at different depths is specific to Uzynbulak, which indicates a unified precipitation recharge system and an active link between the upper and fractured horizons. In the waters of the Baytles creek, an increase in 3H activity is observed with depth, indicating the accumulation of radionuclides in underground horizons with a more dynamic dilution of surface waters. At the same time, the Toktakushuk creek shows the opposite picture: high concentrations are recorded in surface and ground waters at low values in fractured horizons, reflecting the isolation of deep water-bearing systems from contamination processes.
6) New information was obtained on the hydrology of surface waters in the area, including the location and volume of water masses, temporal variability in flow, new data and information on the hydrogeochemistry of the area, which are important for assessing the safety and design of the repository. The geotechnical characteristics of rocks and the chemical composition of groundwater in the areas were studied. The computer database for constructing a hydroisohypse map of the area indicating the direction of groundwater flow was updated.
Section 04 ‘Development of nuclear events and radiation accidents monitoring system’:
1) The radiological situation around sttlements has been studied (assessment of the air basin, objects of water use, farm products contamination). The figures have been obtained on the content of radionuclides in the air (137Cs – <2,1×10-5 Bq/m3, 241Am – <1,0×10-5 Bq/m3, 239+240Pu – from 3,0×10-9 to 6,0×10-7 Bq/m3), in the objects of water use (60Co – <0,4 Bq/kg, 152Eu – <0,4 Bq/kg, 40K – <24 Bq/kg, 238U – <3,0 Bq/kg, 137Cs – <3,0 Bq/kg, 241Am – <0,3 Bq/kg, 235U – <3,0 Bq/kg, 226Ra – <0,4 Bq/kg, 3H – <6,0 Bq/kg), farm products (in the biosamples, 40K – from 1000±200 to 1700±300 Bq/kg, 232Th – <0,4 Bq/kg до 3,7±0,7 Bq/kg, 137Cs – <0,5 Bq/kg, 241Am – <0,5 Bq/kg, 60Co – <0,4 Bq/kg, 152Eu – <0,9 Bq/kg, 154Eu – <1,3 Bq/kg, 238U –<4,9 Bq/kg, 14С – <2,4 Bq/kg, 239+240Pu – 0,3 Bq/kg; in the samples of crop prodcuts, 40K – from 250±50 to 1400±300 Bq/kg, 232Th – from <4,3 Bq/kg to 5,8±3,5 Bq/kg, 137Cs – <1,6 Bq/kg, 241Am – <2,4 Bq/kg, 60Co – <0,8 Bq/kg, 152Eu – <2,3 Bq/kg, 154Eu – <4,7 Bq/kg, 238U – <23 Bq/kg, 235U – <6,9 Bq/kg.). The range of radon EEVA and VA measurements in basements of residential buildings vary from <4 to 81 Bq/m3 and from 42 to 144 Bq/m3, in administrative buildings – from 16 to 215 Bq/m3 and from 107 to 246 Bq/m3, respectively. The transfer factors have been calcualted.
2) The features of the accumulation of radionuclides by individual representatives of the live ground cover and their individual parts were revealed – a descending series of 239+240Pu Tf for spirea (Spiraea hypericifolia): roots > stems, leaves > flowers. The mean value of 241Am Tf is higher than that of 239+240Pu, however, no significant difference in the accumulation has been established. The parameters of the radionuclide transfer to fish have been determined. The mean values of CRорг-корм derived for 137Cs and 90Sr were 0.019 and 1.02, CRорг-сед – 0.027 and 1.91, respectively. The mean value of CRтк-вода was 0.59 (Bq/kg of fresh basis∶Bq/l). As part of the assessment of 3H impact on the morpho-anatomical parameters of haricot (Phaseolus vulgaris), it was found that the mesophyll in the experimental group of the 1st and 2nd generation avaraged 6 and 4% thicker than in the reference group, the upper epidermis’ thickness was 8 and 9%, and that of the lower epidermis was 7 and 6%, respectively. The cytogenetic changes of fescue grass (Festuca valesiaca Gaudin) growing under conditions of radioactive contamination have been confirmed, which shows the usability of this species for bioindication of the habitat quality and individual indicators under conditions of radioactive contamination of terrestrial ecosystems.
3) Methodological approaches to link simulations of biodosimetric triage have been developed, readiness for the operational assessment of individual radiation doses in various scenarios proved, and the practical integration of cytogenetic methods into the emergency response system assured. The experience gained has strengthened the laboratory’s scientific and technical capacity and created the basis to include it in the national radiation safety infrastructure.
4) Field observation data were obtained using a complex of geophysical methods at sites adjacent to the Baikal-1 and VVR-K INP. Technologies for determining the geoelectric and elastic parameters of soils in their natural state, monitoring and processing data on spatio-temporal changes in geoelectric and elastic parameters and gas permeability of the studied sections in conditions of man-made electrical interference, as well as weakly manifested deformation processes, have been improved. A methodical analysis of the informativeness and reliability of geophysical monitoring data has been carried out.
5) Seismic bulletins on nuclear explosions and earthquakes occurred at the STS region have been compiled. The parameters of nuclear explosions and earthquakes occurred at the STS region have been refined. A database of digitized seismograms of peaceful nuclear explosions in the Caspian Depression, Uzbekistan and Turkmenistan has been created.
6) Technical specifications for the development of a prototype measuring complex have been developed. The results of modelling individual components and experimental studies to refine the possible values of certain parameters of the planned measuring complex have been obtained. Schematic diagrams of the planned measuring complex have been developed.
The reliability of the results and conclusions obtained within the framework of the research is ensured by a representative volume of analyzed literature data and a comprehensive review of global experience on the studied topics; the application of well-established research methodologies and approved and certified techniques; the use of mathematically substantiated computational methods and licensed software in theoretical and computational studies; the application of verified and calibrated instrumental and analytical equipment in experimental work, modern methods of statistical data processing, and the consistency of these data with the results of theoretical and computational studies, among other factors.
The research team of this program includes: 1 Doctor of Science, 11 Associate Professors, 3 Candidates of Science, 21 PhD, 15 postgraduate and doctoral students, 45 masters, 13 master’s students. The number of young scientists and specialists (under 35 years old) is 71.
As per 2025 performance results, overall 23 publications, 17 scientific papers of which were prepared. The primary findings of studies have been subjected to scrutiny at International Conferences: XIV International Scientific Conference of young scientists, PhD students, Master`s degree students, and students «Actual environmental problems» (Belarus), XX International Scientific Conference among students, masters and youth scientists “Lomonosov – 2025” (Russia), International Conference on Radiation Applications, RAP 2025 (Greece), the 13th International Conference on Radiation Natural Sciences, Medicine, Engineering, Technology and Ecology (Montenegro).