Management of the Energy and Economic Potential of Nuclear Waste Use

: Recently, issues related to the effects (beneﬁt or harm) of processing nuclear waste and its further use as fuel have been increasingly often raised in the scientiﬁc discussion. In this regard, the research aims to investigate issues related to the assessment of the economic potential of nuclear waste use, as well as the cooperation between states in the context of the reduction of risks associated with nuclear waste storage and processing. The research methodology is based on an integrated approach, including statistical, factor analysis, and the proposed system of performance indicators for managing spent nuclear fuel use. The research was carried out on the basis of materials from Russia and the EU countries. In the course of the study, a model of cooperation between states has been developed (based on the example of technologies and methods of processing nuclear waste used in the EU and Russia) according to the nuclear waste (spent nuclear fuel) management algorithm. The model considers the risks and threats associated with ecology and safety. The developments and other results described in the study should be used in further research devoted to the use of nuclear waste as heat-producing elements.


Introduction
The need to search for new sources of fuel and the disposal of hazardous nuclear waste are raising serious issues associated with the use of spent nuclear fuel. It should be noted that this issue has a dual economic nature. On the one hand, spent nuclear fuel is a rather dangerous type of energy waste requiring expensive disposal; on the other hand, it can be considered as a source of a number of important fuel elements and isotopes that can be used in heating processes [1,2].
Thus, at the moment, many developed and developing countries that have the potential for the development of nuclear energy are faced with a dilemma whether it is necessary to dispose of nuclear waste or to develop methods and technologies for its processing and further use [3,4].
Spent nuclear fuel is most often defined as heat-generating elements removed from the radiation zone, as well as groups of elements that nuclear power plant reactors and other installations are made of [5,6].
The results of the theoretical analysis of terms and approaches to the definition of the concept indicate that spent nuclear fuel can be described as activities that may be associated with processing, reprocessing, transportation, storage, and disposal of fuel elements, in particular, reactive ones [7][8][9][10].
It should be noted that when considering the operation of power plants that rely on fossil fuels or alternative ("clean", renewable, including green) fuels, nuclear power plants As for Russia, the country cooperates with Poland in the transportation and reprocessing of spent nuclear fuel. Thus, in accordance with an international agreement (USA, Russia, EU), concluded in 2009, and the Russian information sources, the An-124-100 cargo plane delivered highly enriched spent nuclear fuel from one of the Polish research reactors to Yekaterinburg (Russia). The fuel elements were delivered to the Mayak radiochemical plant for further processing [28].
However, at present, although spent nuclear fuel storage processes are well regulated at the national and international level, reprocessing processes are not recognized as completely safe. At the same time, there are no sustainable models of cooperation between states to manage these processes. This also affects the difficulties in assessing the economic potential of spent nuclear fuel use, which, in turn, determines the relevance of the research.
Thus, the purpose of the study is to determine how new nuclear waste processing technologies (REMIX and MOX technologies are considered in the framework of the study) based on cooperation between states with energy and economic potential in the field of nuclear power will help solve the problems associated with logistics and disposal of nuclear waste, as well as present spent nuclear fuel as a new competitive fuel element alongside traditional and renewable energy.
The study aims to: − analyze the current use of nuclear waste (spent nuclear fuel) in the world; − assess the situation in Russia and the EU countries (focus on Poland), as well as analyze the current and possible future cooperation between these countries; − investigate the potential of nuclear waste (spent nuclear fuel) use for further processing to be used in heating processes; − develop a model of cooperation between states (based on the example of nuclear waste processing technologies used in the EU and Russia) for the transportation, storage and processing of nuclear waste (spent nuclear fuel) with due regard to the risks associated with ecology and safety.

Methods
In accordance with the research purpose and objectives, the study examines two of the most effective and commonly implemented nuclear waste (spent nuclear fuel) reprocessing technologies, namely REMIX (Russia) and MOX (Western Europe).
Within the framework of the study, these technologies are considered in the context of comparing their economic and physical (technological) characteristics. Thus, mixed-oxide (MOX) fuel is considered as a type of fuel containing uranium dioxide and plutonium dioxide. Generally, based on the method, plutonium, which is separated from spent fuel in a chemical process, is mixed with uranium in its natural form, enriched or depleted, in accordance with the technology chosen. The Regenerated Mixture of U-PuOx (REMIX) technology fuel is considered as another type of independent fuel element (an alternative to MOX), which is obtained from the undivided mixture of regenerated uranium and plutonium, which is formed as a result of the use of pyrometallurgical spent nuclear fuel processing technology. When using this method, an electric current is required to form the combination of the elements; according to experts, this reduces the risks of plutonium proliferation [11,28]. In general, REMIX fuel can be viewed as a simplified version of MOX fuel. These technologies are discussed in more detail in the Results section.
The research consists of two major stages: The first stage of the study is the assessment of the experience, the level of development of spent nuclear fuel reprocessing technologies in Russia and the EU countries based on the methods of economic and statistical analysis; the feasibility of application of these technologies, their advantages over the nuclear waste disposal and preference for reprocessed nuclear fuel as a fuel element has been evaluated.
Economic and financial analysis tools were used to study and compare the economic and technical characteristics of nuclear waste reprocessed based on these technologies in order to assess the potential of the use of spent nuclear fuel as a "new" fuel element in heating processes.
Next, based on the results and conclusions obtained in the framework of the first stage of the study, a model of cooperation between states with energy and economic potential in the field of nuclear energy was developed with the help of modeling, systematization, and structuring tools in order to organize logistics processes and reprocess nuclear waste (spent nuclear fuel) taking into account environmental and safety risks.

Data Analysis
At present, nuclear reactors mainly require enriched uranium-235. Natural uranium contains only 0.7% of uranium-235, of which 0.5% is used as the rest is lost during isotope separation and goes to waste. Natural uranium is mainly composed of uranium-238, which accounts for 99.3%. In the traditional scheme, uranium-235 is fissioned to generate energy in reactors, and uranium-238 in its pure form is considered useless. The period of use of uranium-235 in a standard reactor is three years, then the reactor can be refueled even if it contains a lot of uranium-238. Spent fuel contains about 95% of its original energy when it is extracted by the nuclear power plant personnel. As a result, only 5% of its energy is used; in other words, about one tenth of uranium ore is converted into fuel and less than one hundredth of the total energy content is used to generate electricity. It should be noted that the current cost of uranium-235 extracted from natural uranium is 25 thousand dollars per 1 kg [12,29].
In 2019, the volume of uranium production in Russia was 2.9 thousand tons, while the consumption in the country is 6.5 thousand tons. The shortage is compensated by imports from the reserve fund created in the period of the USSR. The analysis of economic indicators of costs when using uranium-235 extracted from natural uranium confirms the feasibility of spent nuclear fuel use. The major component of spent nuclear fuel is uranium-238. It accounts for about 94% of the total mass of uranium ore. Compared to other decay products, such as cesium-137 or strontium-90, it can be easily stored for future use in poorly protected facilities taking into account the separation from the rest of the material in the spent fuel. In addition, uranium-238 decays when hit by a fast neutron, i.e., when an atom of uranium-238 absorbs a neutron without splitting, it turns into plutonium-239, which, like uranium-235, supports a chain reaction and can be used to generate energy after reprocessing. The cost of reprocessing 1 kg of spent nuclear fuel ranges from $700 to $2000. A year of operation of the existing nuclear reactors results in up to 10,500 tons of spent nuclear fuel [8,9,30].
Today, Rosatom is preparing to switch to a closed nuclear fuel cycle and to establish industrial production of regenerated mixture (REMIX) fuel. The innovative nuclear fuel is obtained from an undivided mixture of reprocessed uranium and plutonium, which is formed as a result of spent nuclear fuel processing, and a small amount of enriched uranium. According to experts, five REMIX fuel cycles are capable of meeting the needs of Russian NPPs for at least 60 years. Europe uses MOX-fuel (mixed oxides of plutonium and uranium), which involves reprocessing of spent nuclear fuel with accumulated plutonium as a result of irradiation of uranium-238. MOX fuel is widely used in nuclear power plants in Belgium, France, Germany and Switzerland. In Japan, twelve nuclear power plants are also licensed to use MOX fuel, and a MOX fuel fabrication facility is being licensed [31][32][33][34]. In the future, MOX fuel will be adapted for more modern reactors, such as PHWR and LMR. Table 1 shows a summary of the world's MOX fuel fabrication facilities.
MOX fuel is supposed to be used in Russian BN-800 and BN-1200 fast neuron reactors. For this purpose, the mining and chemical combine in Zheleznogorsk, commissioned in 2014, will produce up to 60 million tons of fuel for Russian nuclear power plants per year.
The UK, France, and Japan are also involved in nuclear waste reprocessing; their commercial processing capacity is 600, 400, and 800 tons per year, respectively. The nuclear waste market has been expanding in recent years. This is also facilitated by the growing demand for energy in developing countries and the trend towards nuclear energy Energies 2021, 14, 3709 5 of 14 generated from fossil fuels as a result of concerns about global warming. In addition, stricter regulation associated with the use of efficient fuels allows international nuclear waste companies to gain access to new markets. Figure 1 shows the dynamics of the global spent nuclear fuel market growth. Source: developed by the authors based on data from [35].
The Polish government is also engaged in solving the problem of providing the country with electricity through the use of nuclear energy. PolskaGrupaEnergetyczna-ElektrowniaJdrowa (Kartoszyno, Poland), the company responsible for the Polish nuclear power project, in early 2016 confirmed that two potential sites had been selected for the first nuclear power plant, where further environmental testing would be carried out. Both sites are located in northern Poland, not far from the Baltic Sea. According to the IAEA, Poland has implemented all the recommendations and proposals of the Integrated Nuclear Infrastructure Review Mission (INIR). The representatives of the Polish Ministry of Energy reported that Poland is taking all necessary measures to ensure its nuclear power safety. The program meets the highest standards and international best practices [37].
It should be noted that the global industry and power economy are generally becoming more environmentally friendly and the storage of spent nuclear fuel is an outdated practice; today household and production waste is almost completely processed. The nuclear industry is also switching to the use of 'recyclable materials'. There is another motivationthe reserves of uranium-235 are limited and there is a need for the options of using uranium-238 and thorium-232. The Polish government is also engaged in solving the problem of providing the country with electricity through the use of nuclear energy. PolskaGrupaEnergetyczna-El-ektrowniaJdrowa (Kartoszyno, Poland), the company responsible for the Polish nuclear power project, in early 2016 confirmed that two potential sites had been selected for the first nuclear power plant, where further environmental testing would be carried out. Both sites are located in northern Poland, not far from the Baltic Sea. According to the IAEA, Poland has implemented all the recommendations and proposals of the Integrated Nuclear Infrastructure Review Mission (INIR). The representatives of the Polish Ministry of Energy reported that Poland is taking all necessary measures to ensure its nuclear power safety. The program meets the highest standards and international best practices [37].
It should be noted that the global industry and power economy are generally becoming more environmentally friendly and the storage of spent nuclear fuel is an outdated practice; today household and production waste is almost completely processed. The nuclear industry is also switching to the use of 'recyclable materials'. There is another motivation-the reserves of uranium-235 are limited and there is a need for the options of using uranium-238 and thorium-232.

Results
Let us consider and analyze two major technologies for reprocessing spent nuclear fuel-MOX and REMIX-from the perspective of economic and technical characteristics.
Currently, it is MOX fuel that is reused in Europe. In addition, a number of European countries (Poland, France, Germany) often act as suppliers of MOX fuel or nuclear waste in the form of raw materials for other processing technologies (for example, cooperation between Poland and Russia).
In accordance with technical characteristics and properties, MOX fuel is most often used in fast-neutron reactors (for example, BN-600, BN-800, and BN-1200 that is under development, etc.). Reactors of these types can most efficiently use plutonium and make it from uranium [11,34].
REMIX fuel (a Russian development) is still being tested and developed; however, according to the reports of Russian scientists, they will come up with an enhanced version of MOX fuel, which will be characterized by lower production cost, economic consumption, and greater environmental performance (impact on environment).

Results
Let us consider and analyze two major technologies for reprocessing spent nuclear fuel-MOX and REMIX-from the perspective of economic and technical characteristics.
Currently, it is MOX fuel that is reused in Europe. In addition, a number of European countries (Poland, France, Germany) often act as suppliers of MOX fuel or nuclear waste in the form of raw materials for other processing technologies (for example, cooperation between Poland and Russia).
In accordance with technical characteristics and properties, MOX fuel is most often used in fast-neutron reactors (for example, BN-600, BN-800, and BN-1200 that is under development, etc.). Reactors of these types can most efficiently use plutonium and make it from uranium [11,34].
REMIX fuel (a Russian development) is still being tested and developed; however, according to the reports of Russian scientists, they will come up with an enhanced version of MOX fuel, which will be characterized by lower production cost, economic consumption, and greater environmental performance (impact on environment).
The study considered the technological features of nuclear fuel processing according to MOX and REMIX, which are shown in Figure 2. The study considered the technological features of nuclear fuel processing according to MOX and REMIX, which are shown in Figure 2.  The main distinguishing feature of the technologies presented is that REMIX-fuel can be reprocessed repeatedly at 100% core fill in operating WWER and, therefore, can be used repeatedly up to five times, so that with less than three fuel loadings a reactor can operate The main distinguishing feature of the technologies presented is that REMIX-fuel can be reprocessed repeatedly at 100% core fill in operating WWER and, therefore, can be used repeatedly up to five times, so that with less than three fuel loadings a reactor can operate for 60 years using this fuel. The use of REMIX fuel, like MOX fuel, reduces the consumption of natural uranium in WWER reactors by about 20% per recycle, as opposed to the open fuel cycle. REMIX can be used as a replacement for existing reactor fuels, but unlike MOX fuel, due to its high activity, the cost of fuel production is higher, with a cost increase of up to 25-30%. If necessary, the REMIX cycle can be converted. Table 2 shows the results of the comparison of the major economic and technical characteristics of REMIX (Russia) and MOX (EU) fuel. A type of fuel that is obtained from the undivided mixture of reprocessed uranium and plutonium, which is formed as a result of the use of pyrometallurgical spent nuclear fuel processing technology.

Spent
A type of fuel that contains uranium dioxide and plutonium. Plutonium, which is separated from spent fuel in a chemical process, is mixed with uranium in its natural, enriched or depleted form, in accordance with the technology chosen. As can be seen, the advantages of nuclear waste (spent nuclear fuel) reprocessing are characteristic of both MOX and REMIX fuel. The key difference between REMIX fuel and MOX fuel is the fact that in production, uranium and plutonium contained in the fuel produced using either technology are not separated. REMIX fuel does not have enough fissile nuclides, and therefore plutonium or enriched uranium is added.
The REMIX technology ensures a higher conservation rate of natural uranium compared to the open nuclear fuel cycle (OFC); however, given the wider distribution of MOX fuel in the world and the fact that REMIX is still at the development stage, more accurate results will be obtained later.
The price range varies due to the diversity of reactors producing the finished product; however, when compared with the generation of energy in the process of a more toxic open nuclear cycle, the price of fuel manufactured based on both technologies exceeds the cost of the OFC by 5-7 times.
It should be noted that despite the current uncertainty, the assessment of the potential of the REMIX technology to use spent nuclear fuel is higher than that of the MOX technology. First of all, this is due to the fact that the volume of uranium production in Russia in 2017-2018 amounted to about 2.9-3.0 thousand tons while the level of consumption was 6.5-7 thousand tons, including the coverage of the deficit by imports and the reserve fund; thus, according to Russian estimates, thousands of tons of spent nuclear fuel accumulated over many years of the Russian nuclear industry operation and the use of a five-cycle fuel processing technology can meet the needs of both the Russian and world energy markets for many decades to come.
The advantages of closed fuel cycle technologies (MOX, REMIX) over the traditional open cycle fuel technology that is more toxic should also be mentioned. According to the methodology for calculation of recycles with REMIX fuel, the following parameters were calculated, which were further used to estimate natural uranium consumption: fuel consumption and enrichment, as well as consumption of uranium-plutonium regenerate. These parameters are shown in Table 3 and presented in tons per year (for 42 fuel assemblies). Thus, based on the data given in Table 3, Figures 3 and 4 show the data on the consumption of natural uranium, separative work units, and natural uranium conservation in comparison with an open nuclear fuel cycle. It should be noted that in an open fuel cycle, spent nuclear fuel is considered to be highly radioactive waste, which is excluded from further use along with residual fissile isotopes and goes to storage or disposal facilities.  To assess the effect of reactor campaign duration on the efficiency of a closed nuclear fuel cycle with REMIX fuel, 5-recycle calculations were performed using the fresh fuel isotopic composition approach. The isotopic composition for the 1st recycle was formed on the basis of reprocessing of spent regular uranium fuel with the average burnup of the fuel assemblies unloaded during the one and a half year reactor campaign. The average burnup of the unloaded fuel assemblies was 49.4 MWd/kgHM. The average enrichment for the standard WWER-1000 uranium load in this case was ~4.75%. The corresponding indicators for five cycles of nuclear waste use have been determined. Thus, it is possible to estimate the correlation between the amount of cost reduction and natural uranium savings. The results indicate reduced costs and increased savings of natural uranium, fuel assemblies unloaded during the one and a half year reactor campaign. The average burnup of the unloaded fuel assemblies was 49.4 MWd/kgHM. The average enrichment for the standard WWER-1000 uranium load in this case was ~4.75%. The corresponding indicators for five cycles of nuclear waste use have been determined. Thus, it is possible to estimate the correlation between the amount of cost reduction and natural uranium savings. The results indicate reduced costs and increased savings of natural uranium, which confirms savings of 20-30% (Figure 4).  To assess the effect of reactor campaign duration on the efficiency of a closed nuclear fuel cycle with REMIX fuel, 5-recycle calculations were performed using the fresh fuel isotopic composition approach. The isotopic composition for the 1st recycle was formed on the basis of reprocessing of spent regular uranium fuel with the average burnup of the fuel assemblies unloaded during the one and a half year reactor campaign. The average burnup of the unloaded fuel assemblies was 49.4 MWd/kgHM. The average enrichment for the standard WWER-1000 uranium load in this case was~4.75%. The corresponding indicators for five cycles of nuclear waste use have been determined. Thus, it is possible to estimate the correlation between the amount of cost reduction and natural uranium savings. The results indicate reduced costs and increased savings of natural uranium, which confirms savings of 20-30% ( Figure 4).
As can be seen, closed fuel cycle technologies are more cost-effective. The change in the separative work unit when testing the REMIX method also confirms the advantages noted above.
In general, according to the analysis method tested in the study, REMIX fuel can save natural uranium by 20-30% in comparison with the OFC. The results of the end-to-end nuclear fuel cycle analysis (based on the analysis of the MOX and REMIX methods) indicate that recently mixed schemes have been most commonly found in the internal and external energy markets of both developed and developing countries. Thus, for example, MOX fuel is characterized by the division of economies into states supplying raw materials, states dealing with processing and states supplying the finished product to the markets. At the same time, given the fact that REMIX fuel is still being developed, Russia acts as a producer and supplier of both raw materials and a finished product.
A model of cooperation between states describing the algorithm of nuclear waste (spent nuclear fuel) management is given below. Within the framework of the model, the key element is the risk regulators, which include methods and tools that will help states prevent major risks and threats associated with the operation and use of spent nuclear fuel and perform various functions in the process of preparation, processing and market distribution of reprocessed nuclear waste as an element that is reused in the energy sector (in particular, in heating processes) ( Figure 5).
A model of cooperation between states describing the algorithm of nuclear waste (spent nuclear fuel) management is given below. Within the framework of the model, the key element is the risk regulators, which include methods and tools that will help states prevent major risks and threats associated with the operation and use of spent nuclear fuel and perform various functions in the process of preparation, processing and market distribution of reprocessed nuclear waste as an element that is reused in the energy sector (in particular, in heating processes) ( Figure 5).

Discussion
In the context of spent nuclear fuel management, studies, speeches and press releases of politicians, public figures, and forums of international organizations, are mainly associated with the analysis of the end-to-end nuclear fuel cycle and the feasibility of including an additional waste processing process in its structure for secondary use in heating processes. In addition, scientific community is increasingly focused on the study of the issues of disposal and transportation of spent nuclear fuel. It is often noted that despite the fact that a third of the spent fuel accumulated in the world is subject to reprocessing, its major part is stored until a decision is made on what to do with it-reprocess or dispose of it. It is determined by such factors as political strategies, technology development, stages of the nuclear fuel cycle, the choice of its final stage (reprocessing or disposal), etc. [40,41].
Another line of discourse concerns the safety of further use of nuclear waste. It should be noted that in the context of the production cycle safety, many experts agree that the hazards of the end-to-end nuclear fuel cycle can be reduced through careful observance of safety rules, labor protection, production regulations, etc. [27,28,42]. In particular, when working with spent nuclear fuel, it is important to take into account the factors of reliability, lean production, as well as to ensure proper storage of waste after removing it from the radiation zone for the purpose of further reprocessing or, in case of unsuitability, final disposal [43,44]. Safe, reliable, resilient, and cost-effective nuclear fuel cycles that can minimize hazardous waste generation and environmental impact contribute to the global sustainability of nuclear power [45,46].
In scientific and practical (business format) discussions, the importance of cooperation between states in the context of the application of new best practices and the exchange of experience in the field of spent nuclear fuel management is highlighted [47,48]. Thus, an international legal framework should be developed. For example, the Joint Convention on the Safety of Spent Fuel and Radioactive Waste Management [21,24] contains both recommendations and mandatory requirements, in particular for the states that have signed this document. The main objectives are to improve the capacity to plan, develop and implement safe, environmentally friendly and effective strategies and technologies for the management of spent nuclear fuel. In addition, one of the major tasks of cooperation between states is the need to identify and solve technological problems related to the use of spent nuclear fuel, management flexibility, and the analysis of future scenarios [32,49]. It should be noted that these theses are in line with our study, which describes a model of cooperation between states in the context of spent nuclear fuel reprocessing and storage management.
One of the obstacles to cooperation between states in the context of spent nuclear fuel management may be fears of political leaders about the possibility of using nuclear waste to produce nuclear weapon [20] In addition, there are no perfect technologies for the transportation and storage of nuclear waste to be further reprocessed. It is said that spent fuel storage systems may need to be serviced for longer periods of time, which stimulates research and the development of programs to manage the logistics of spent nuclear fuel [34,50].
As for the discussion about the advantages of REMIX and MOX fuel, which are also considered in the framework of our study, it should be noted that in Russia, the preference is given to REMIX-technologies while in Western countries, on the contrary, the MOX technology is mainly used. At the same time, other more sophisticated processing technologies are being developed in some countries in order to reuse fertile (minor actinides, such as neptunium, americium and curium) and / or long-lived radionuclides (such as cesium and strontium) to make the nuclear fuel cycle more sustainable and to reduce the amount and radiotoxicity of the final waste to be disposed of. These technologies can be used in reactors in the long term [20,30].

Conclusions
The results obtained in the course of the study indicate that on a global scale industry and energy are gradually becoming more environmentally friendly, and emissions of toxic industrial waste into the atmosphere are decreasing. Within the framework of this paradigm, the approach to the storage (disposal) of nuclear fuel waste can be considered outdated. Both developed (for example, EU countries) and developing countries (Russia) are gradually switching to the use of nuclear fuel waste reprocessing models. In addition, there is another important motive-the depletion of uranium reserves in the world. A complete transition to renewable energy in the coming decades is not possible, and this issue is still somewhat controversial.
In western markets, spent nuclear fuel that has been reprocessed-MOX fuel-is used. At the same time, Russia is developing a more economical and environmentally friendly REMIX fuel. According to Russian scientists, the introduction of fuel processed with the help of this technology can bring significant effects. In particular, the study results allow concluding that reprocessing based on the REMIX technology with the possibility of multiple use of nuclear fuel will significantly reduce the amount of recovered uranium, plutonium waste, and natural uranium consumption by almost 20-30%. The use of this technology provides a real opportunity and expediency to reduce the nuclear fuel cycle.
A closed fuel cycle technology (based on the example of the MOX and REMIX fuel) has significant advantages over the highly toxic and more hazardous open cycle from the point of view of production safety. This creates a strategic basis for the development of nuclear energy in the long term.
At the same time, it is important to develop a stable spent nuclear fuel management policy, which will solve the strategic tasks of the power industry and reduce current risks and threats.
Thus, the research results make it clear that the potential of nuclear waste (spent nuclear fuel) use for further processing to be used in heating processes is significant, but it takes time to regulate energy markets taking into account the emergence of a new product-reprocessed nuclear fuel waste-and stabilize political issues in this regard.
An important result of the work is the development of a model of cooperation between states describing the algorithm of nuclear waste (spent nuclear fuel) management taking into account the risks and threats associated with the environment and safety. This study proves the real possibility and feasibility of closing the nuclear fuel cycle, which can be recommended for inclusion in the complex of a modern strategy for long-term energy security. The study confirms the importance of cooperation between states in the context of applying new best practices and experience exchange in nuclear waste management. The research results not only suggest a recommendation but an objective need to develop the international legal framework.
In general, it can be said that the developments and results described in the study are recommended for use in further research on the potential of the use of nuclear waste in energy processes and nuclear power industry. In the future, the study can assess the impact of energy and economic potential of nuclear waste management on the sustainable development of countries and regions. At the same time, it is advisable to develop methodological tools for assessing recycling activities' efficiency, as well as to form strategic initiatives at a state level that can contribute to solving global nuclear waste problems.
In the future, the study can be expanded to determine the impact of nuclear waste management on the sustainable development of countries and regions, and to increase the effectiveness of long-term energy security in a dual context. This implies further research towards both minimization of natural uranium consumption and scenario modeling of REMIX transition options and replacement of existing reactor fuels.