Pub Date : 2024-03-12DOI: 10.1134/s1066362223070044
N. A. Bezhin, I. G. Tananaev
Abstract
The results of cesium recovery from seawater with commercially available Termoxid sorbents (Termoxid 35, Termoxid 3A) under laboratory and expeditionary conditions are presented. The dynamic exchange capacity and the total dynamic exchange capacity of the sorbents for cesium were determined. The breakthrough curves of cesium sorption were plotted for different seawater flow rates, and the physicochemical relationships (isotherm and kinetics) of sorption were studied. The efficiency of 137Cs recovery from large volumes of seawater by Termoxid sorbents under expeditionary conditions was evaluated.
{"title":"Cesium-137 Recovery from Seawater by Sorption onto Termoxid Sorbents","authors":"N. A. Bezhin, I. G. Tananaev","doi":"10.1134/s1066362223070044","DOIUrl":"https://doi.org/10.1134/s1066362223070044","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>The results of cesium recovery from seawater with commercially available Termoxid sorbents (Termoxid 35, Termoxid 3A) under laboratory and expeditionary conditions are presented. The dynamic exchange capacity and the total dynamic exchange capacity of the sorbents for cesium were determined. The breakthrough curves of cesium sorption were plotted for different seawater flow rates, and the physicochemical relationships (isotherm and kinetics) of sorption were studied. The efficiency of <sup>137</sup>Cs recovery from large volumes of seawater by Termoxid sorbents under expeditionary conditions was evaluated.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140889127","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-03-12DOI: 10.1134/s1066362223070202
S. M. Shaydullin, P. V. Kozlov, M. B. Remizov
Abstract
TThe paper justifies great practical relevance of the problem of corrosion and erosion resistance of the refractories used as a structural element in direct electric heating furnaces intended for high-level waste vitrification. The list of the main promising materials is provided, as well as the algorithm of assessing their resistance to borosilicate melts during operation of electric furnaces. Corrosion tests of the refractory materials were carried out under static and dynamic conditions in low-melting borosilicate glass and in the melt of borosilicate glass containing simulated liquid high-level waste (HLW). The refractories that are most resistant to the glass melt under conditions of HLW solidification were identified. The results obtained will be useful for selecting the lining material for removable and small-size melters.
{"title":"Corrosion Tests of Domestic and Imported Chromium-Containing and Baddelyite–Corundum Refractories in Borosilicate Glass Melts","authors":"S. M. Shaydullin, P. V. Kozlov, M. B. Remizov","doi":"10.1134/s1066362223070202","DOIUrl":"https://doi.org/10.1134/s1066362223070202","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>TThe paper justifies great practical relevance of the problem of corrosion and erosion resistance of the refractories used as a structural element in direct electric heating furnaces intended for high-level waste vitrification. The list of the main promising materials is provided, as well as the algorithm of assessing their resistance to borosilicate melts during operation of electric furnaces. Corrosion tests of the refractory materials were carried out under static and dynamic conditions in low-melting borosilicate glass and in the melt of borosilicate glass containing simulated liquid high-level waste (HLW). The refractories that are most resistant to the glass melt under conditions of HLW solidification were identified. The results obtained will be useful for selecting the lining material for removable and small-size melters.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140115166","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-03-12DOI: 10.1134/s1066362223070093
Yu. G. Mokrov
Abstract
In the 1950s, V-2 reservoir (Lake Kyzyl-Tash) was used for cooling industrial uranium–graphite reactors (IUGRs). When water passed through the IUGR core, activation radionuclides (ARs) were produced by nuclear reactions of reactor neutrons with nuclei of chemical elements present in water and were accumulated in water. The AR activity concentration in water from V-2 reservoir depends on the concentration of chemical elements in the reservoir. Data on the content of 16 elements in V-2 water in the period 1948–1956 were collected. These data were analyzed taking into account the characteristic natural abundance of elements in water of the Irtyash–Kasli lake system and the additional technogenic pollution of the reservoir in the course of its operation. The main source of AR transfer from V-2 reservoir to the Techa River was controlled water discharge through open shutters of the P-2 dam (or uncontrolled water seepage through closed shutters). A mathematical model was suggested, and the activity concentrations in V-2 water were calculated for 16 elements and 31 nuclear reactions yielding 20 ARs. The model was verified using the archive data on the activity concentrations of 32Р in V-2 water in 1953–1956. All the calculation results well agree with the available experimental data. The source term for AR transfer from V-2 reservoir to the Techa River in relation to the water flow rate through P-2 dam was determined. The experimental data on the scale of the distribution of the 32Р activity concentration along the Techa River were analyzed. The results obtained allow taking into account the AR contribution to the total radioactive pollution of the river and evaluating the possible radiation impact on the population and biota.
{"title":"Evaluation of Source Term for the Supply of Activation Radionuclides into the Techa River","authors":"Yu. G. Mokrov","doi":"10.1134/s1066362223070093","DOIUrl":"https://doi.org/10.1134/s1066362223070093","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>In the 1950s, V-2 reservoir (Lake Kyzyl-Tash) was used for cooling industrial uranium–graphite reactors (IUGRs). When water passed through the IUGR core, activation radionuclides (ARs) were produced by nuclear reactions of reactor neutrons with nuclei of chemical elements present in water and were accumulated in water. The AR activity concentration in water from V-2 reservoir depends on the concentration of chemical elements in the reservoir. Data on the content of 16 elements in V-2 water in the period 1948–1956 were collected. These data were analyzed taking into account the characteristic natural abundance of elements in water of the Irtyash–Kasli lake system and the additional technogenic pollution of the reservoir in the course of its operation. The main source of AR transfer from V-2 reservoir to the Techa River was controlled water discharge through open shutters of the P-2 dam (or uncontrolled water seepage through closed shutters). A mathematical model was suggested, and the activity concentrations in V-2 water were calculated for 16 elements and 31 nuclear reactions yielding 20 ARs. The model was verified using the archive data on the activity concentrations of <sup>32</sup>Р in V-2 water in 1953–1956. All the calculation results well agree with the available experimental data. The source term for AR transfer from V-2 reservoir to the Techa River in relation to the water flow rate through P-2 dam was determined. The experimental data on the scale of the distribution of the <sup>32</sup>Р activity concentration along the Techa River were analyzed. The results obtained allow taking into account the AR contribution to the total radioactive pollution of the river and evaluating the possible radiation impact on the population and biota.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140115173","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-03-12DOI: 10.1134/s106636222307010x
Yu. G. Mokrov
Abstract
The study is aimed at reconstructing the parameters of the source from which the people living in 1949–1956 on the banks of the Techa River were irradiated. It deals with the migration of γ-emitting nuclides (GENs) and specifically 95Nb in the river water. Some assumptions concerning the sources from which 95Nb got into the river water and its migration with the river flow were made previously. It was noted that the 95Nb sorbability is abnormally low and it is readily transported over long distances with the river water, whereas 95Zr, on the contrary, is efficiently taken up by bottom sediments already at the point of the liquid radioactive waste (LRW) discharge and can migrate only in the form of suspended material or bed load. It was noted that 95Nb could get into the river water both directly with the discharged LRW (external source) and via release from bottom sediments (BSs) after the 95Zr decay (internal source). It was assumed that, after October 1951 when the LRW discharge into the river was reduced by 2–3 orders of magnitude, the internal source became the main source of the 95Nb supply into the river water. This study additionally confirms the above assumptions. Archive results of daily measurements of the water specific activity in 1952 in the upper reaches of the Techa River are considered. The activity concentration of the sum of β-emitting nuclides (BENs), AΣ (μCi/L), was determined by measuring the β-particle count rate with an end-window counter, and that of the sum of γ-emitting nuclides (GENs), МΣ (μg-equiv Ra/L), by comparing the ionizing power of the test and reference (226Ra) sources. In determining the activity concentration of jth BEN, the β-radiation absorption coefficient in the layer of all the materials between the sample and the end-window counter, Kj, should be taken into account. Determination of the ratio Rj = Мj/Аj = mj/Kj, where mj is the gamma equivalent of jth GEN (μg-equiv Ra/μCi), was suggested for each jth GEN in the discharged LRW. Comparison of the experimental ratios RΣ = МΣ/АΣ with the corresponding calculated values, Rj = mj/Kj, furnishes new valuable information on the 95Nb concentration in the river water. In the first half of the year 1952, the 95Nb activity concentration in river water was more than 10 times higher than the AΣ values measured with an end-window counter (practically, the 95Nb activity was not detected). The main source of the 95Nb
{"title":"Behavior of Niobium-95 in Techa River Water","authors":"Yu. G. Mokrov","doi":"10.1134/s106636222307010x","DOIUrl":"https://doi.org/10.1134/s106636222307010x","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>The study is aimed at reconstructing the parameters of the source from which the people living in 1949–1956 on the banks of the Techa River were irradiated. It deals with the migration of γ-emitting nuclides (GENs) and specifically <sup>95</sup>Nb in the river water. Some assumptions concerning the sources from which <sup>95</sup>Nb got into the river water and its migration with the river flow were made previously. It was noted that the <sup>95</sup>Nb sorbability is abnormally low and it is readily transported over long distances with the river water, whereas <sup>95</sup>Zr, on the contrary, is efficiently taken up by bottom sediments already at the point of the liquid radioactive waste (LRW) discharge and can migrate only in the form of suspended material or bed load. It was noted that <sup>95</sup>Nb could get into the river water both directly with the discharged LRW (external source) and via release from bottom sediments (BSs) after the <sup>95</sup>Zr decay (internal source). It was assumed that, after October 1951 when the LRW discharge into the river was reduced by 2–3 orders of magnitude, the internal source became the main source of the <sup>95</sup>Nb supply into the river water. This study additionally confirms the above assumptions. Archive results of daily measurements of the water specific activity in 1952 in the upper reaches of the Techa River are considered. The activity concentration of the sum of β-emitting nuclides (BENs), <i>A</i><sub>Σ</sub> (μCi/L), was determined by measuring the β-particle count rate with an end-window counter, and that of the sum of γ-emitting nuclides (GENs), <i>М</i><sub>Σ</sub> (μg-equiv Ra/L), by comparing the ionizing power of the test and reference (<sup>226</sup>Ra) sources. In determining the activity concentration of <i>j</i>th BEN, the β-radiation absorption coefficient in the layer of all the materials between the sample and the end-window counter, <i>K</i><sub><i>j</i></sub>, should be taken into account. Determination of the ratio <i>R</i><sub><i>j</i></sub> = <i>М</i><sub><i>j</i></sub><i>/А</i><sub><i>j</i></sub> = <i>m</i><sub><i>j</i></sub><i>/K</i><sub><i>j</i></sub>, where <i>m</i><sub><i>j</i></sub> is the gamma equivalent of <i>j</i>th GEN (μg-equiv Ra/μCi), was suggested for each <i>j</i>th GEN in the discharged LRW. Comparison of the experimental ratios <i>R</i><sub>Σ</sub><i> = М</i><sub>Σ</sub>/<i>А</i><sub>Σ</sub> with the corresponding calculated values, <i>R</i><sub><i>j</i></sub><i> = m</i><sub><i>j</i></sub><i>/K</i><sub><i>j</i></sub>, furnishes new valuable information on the <sup>95</sup>Nb concentration in the river water. In the first half of the year 1952, the <sup>95</sup>Nb activity concentration in river water was more than 10 times higher than the <i>A</i><sub>Σ</sub> values measured with an end-window counter (practically, the <sup>95</sup>Nb activity was not detected). The main source of the <sup>95</sup>Nb ","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140115470","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-03-12DOI: 10.1134/s1066362223070135
S. S. Poglyad, O. S. Dmitrieva, E. A. Bezdnyakova, O. V. Romanova
Abstract
The applicability of bentonite clay-based ceramics for immobilization of waste from pyrochemical reprocessing of spent nuclear fuel–spent electrolyte, which consists of alkali metal chlorides, was studied. Main matrix characteristics such as the phase composition, mechanical durability, leaching rate and microstructure were studied. The results obtained were compared to the requirements to the cement compound, formulated in NP-019-15 document. The matrix was considered to be suitable for the radioactive waste disposal.
{"title":"Assessment of Applicability of Bentonite Clay-Based Ceramics for Immobilization of Radioactive Waste from Pyrochemical Processing of Spent Nuclear Fuel","authors":"S. S. Poglyad, O. S. Dmitrieva, E. A. Bezdnyakova, O. V. Romanova","doi":"10.1134/s1066362223070135","DOIUrl":"https://doi.org/10.1134/s1066362223070135","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>The applicability of bentonite clay-based ceramics for immobilization of waste from pyrochemical reprocessing of spent nuclear fuel–spent electrolyte, which consists of alkali metal chlorides, was studied. Main matrix characteristics such as the phase composition, mechanical durability, leaching rate and microstructure were studied. The results obtained were compared to the requirements to the cement compound, formulated in NP-019-15 document. The matrix was considered to be suitable for the radioactive waste disposal.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140127263","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-03-12DOI: 10.1134/s106636222307007x
V. E. Eremyashev, G. G. Korinevskaya, M. A. Rassomakhin, D. E. Zhivulin, S. M. Shaidullin, P. V. Kozlov
Abstract
Zirconium is one of critical high-level waste components that get into the glass and affect its properties. There are various zirconium sources such as partial corrosion damage of fuel rod clads in the course of SNF reprocessing or dissolution of the zirconium-containing refractory material of the glass-making furnace in the glass melt. Furthermore, zirconium is present in SNF as a fission product. Dissolution of zirconium in aluminoborosilicate glasses developed as a host material for high-level waste vitrification was studied by electron microscopy. The zirconium distribution between the glass and crystalline phases was studied. The optimum component ratio ensuring maximal incorporation of zirconium into the glass-containing fraction of the host material was determined. The results obtained can serve as a basis for adjusting the synthesis parameters of glass-containing borosilicate host materials used for immobilization of zirconium-containing high-level waste.
{"title":"Limiting Solubility of Zirconium in Aluminoborosilicate Glasses","authors":"V. E. Eremyashev, G. G. Korinevskaya, M. A. Rassomakhin, D. E. Zhivulin, S. M. Shaidullin, P. V. Kozlov","doi":"10.1134/s106636222307007x","DOIUrl":"https://doi.org/10.1134/s106636222307007x","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>Zirconium is one of critical high-level waste components that get into the glass and affect its properties. There are various zirconium sources such as partial corrosion damage of fuel rod clads in the course of SNF reprocessing or dissolution of the zirconium-containing refractory material of the glass-making furnace in the glass melt. Furthermore, zirconium is present in SNF as a fission product. Dissolution of zirconium in aluminoborosilicate glasses developed as a host material for high-level waste vitrification was studied by electron microscopy. The zirconium distribution between the glass and crystalline phases was studied. The optimum component ratio ensuring maximal incorporation of zirconium into the glass-containing fraction of the host material was determined. The results obtained can serve as a basis for adjusting the synthesis parameters of glass-containing borosilicate host materials used for immobilization of zirconium-containing high-level waste.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140115715","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-03-12DOI: 10.1134/s1066362223070111
Yu. G. Mokrov
Abstract
The study is aimed at the source-term reconstruction for the exposure of people to ionizing radiation who lived in 1949–1956 on the Techa riverside. It deals with the migration of γ-emitting nuclides (GENs), and specifically 95Zr and 95Nb, in the river system. It is known that 95Zr exhibits abnormally high sorption properties and is virtually completely and irreversibly sorbed onto bottom sediments (BSs) and suspended material already near the liquid radioactive waste (LRW) discharge site. Therefore, its further migration is possible only with the solid runoff. It was shown previously that the large-scale radioactive contamination of the river occurred in the relatively short period from July to October 1951, when the water flow rate in the upper section was varied from 8 to 30 m3/s. Under such water runoff conditions, the most contaminated BSs near the LRW discharge site undergo intense stirring-up (erosion), and the resulting suspensions are transferred with gradual sedimentation of the suspended material throughout the river stretch. After October 1951, when the LRW discharge into the river decreased by 2–3 orders of magnitude, the 95Zr distribution in BSs was determined only by the radioactive decay and transfer of suspended matters and saltation loads. Specific features of methods used in the 1950s for measuring the specific activity of the sum of β-emitting nuclides (BENs, AΣ, μCi/kg) and sum of GENs (МΣ, μg-equiv Ra/kg) are discussed. The use of the ratio RΣ = МΣ/АΣ as a criterion furnishes new information on the 95Zr activity concentration in BSs and allows picking out BS samples with prevalent contributions of 95Zr (МZr) и 95Nb (МNb) to МΣ from the whole set of the archive data. Analysis of the measured archive data on the specific activity of BS samples taken from different sections of the Techa River in 1952, 1954, and 1955 using the criterion RΣ = МΣ/АΣ allowed estimation of МΣ ≈ МZr + МNb and recalculation of these results taking into account the radioactive decay as of November 1, 1951. The results of MΣ measurements performed in 1952, 1954, and 1955 and converted to the level of November 1, 1951 appeared to be close, although the absolute activity level decreased by a factor of up to ~10 mln owing to radioactive decay. The 95Zr specific activity in the river BSs as of November 1951 remained virtually constant throughout the river stretch. These results provide a new approach to reconstruction of the external dose for the Techa riverside population.
{"title":"Zirconium-95 Distribution in Bottom Sediments of the Techa River in 1952–1955","authors":"Yu. G. Mokrov","doi":"10.1134/s1066362223070111","DOIUrl":"https://doi.org/10.1134/s1066362223070111","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>The study is aimed at the source-term reconstruction for the exposure of people to ionizing radiation who lived in 1949–1956 on the Techa riverside. It deals with the migration of γ-emitting nuclides (GENs), and specifically <sup>95</sup>Zr and <sup>95</sup>Nb, in the river system. It is known that <sup>95</sup>Zr exhibits abnormally high sorption properties and is virtually completely and irreversibly sorbed onto bottom sediments (BSs) and suspended material already near the liquid radioactive waste (LRW) discharge site. Therefore, its further migration is possible only with the solid runoff. It was shown previously that the large-scale radioactive contamination of the river occurred in the relatively short period from July to October 1951, when the water flow rate in the upper section was varied from 8 to 30 m<sup>3</sup>/s. Under such water runoff conditions, the most contaminated BSs near the LRW discharge site undergo intense stirring-up (erosion), and the resulting suspensions are transferred with gradual sedimentation of the suspended material throughout the river stretch. After October 1951, when the LRW discharge into the river decreased by 2–3 orders of magnitude, the <sup>95</sup>Zr distribution in BSs was determined only by the radioactive decay and transfer of suspended matters and saltation loads. Specific features of methods used in the 1950s for measuring the specific activity of the sum of β-emitting nuclides (BENs, <i>A</i><sub>Σ</sub>, μCi/kg) and sum of GENs (<i>М</i><sub>Σ</sub>, μg-equiv Ra/kg) are discussed. The use of the ratio <i>R</i><sub>Σ</sub><i> = М</i><sub>Σ</sub>/<i>А</i><sub>Σ</sub> as a criterion furnishes new information on the <sup>95</sup>Zr activity concentration in BSs and allows picking out BS samples with prevalent contributions of <sup>95</sup>Zr (<i>М</i><sub>Zr</sub>) и <sup>95</sup>Nb (<i>М</i><sub>Nb</sub>) to <i>М</i><sub>Σ</sub> from the whole set of the archive data. Analysis of the measured archive data on the specific activity of BS samples taken from different sections of the Techa River in 1952, 1954, and 1955 using the criterion <i>R</i><sub>Σ</sub><i> = М</i><sub>Σ</sub>/<i>А</i><sub>Σ</sub> allowed estimation of <i>М</i><sub>Σ</sub> ≈ <i>М</i><sub>Zr</sub> + <i>М</i><sub>Nb</sub> and recalculation of these results taking into account the radioactive decay as of November 1, 1951. The results of <i>M</i><sub>Σ</sub> measurements performed in 1952, 1954, and 1955 and converted to the level of November 1, 1951 appeared to be close, although the absolute activity level decreased by a factor of up to ~10 mln owing to radioactive decay. The <sup>95</sup>Zr specific activity in the river BSs as of November 1951 remained virtually constant throughout the river stretch. These results provide a new approach to reconstruction of the external dose for the Techa riverside population.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140889132","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-03-12DOI: 10.1134/s1066362223070019
I. V. Kapyrin
Abstract
The paper is focused on the problem of groundwater flow and transport modeling applied to safety assessment of nuclear facilities and development of relevant computational codes. The classification of typical tasks of the nuclear industry is provided, and specific features typical of different classes of simulated objects are analyzed, including their near and far fields. The most radioecologically relevant radionuclides are identified for each class. GeRa computational code is used as an example to analyze current trends of the development of hydrogeological modeling software.
摘要 本文主要研究应用于核设施安全评估的地下水流动和传输建模问题，以及相关计算代码的开发。本文对核工业的典型任务进行了分类，并分析了不同类别模拟对象的典型特征，包括它们的近场和远场。确定了每类对象中与放射生态最相关的放射性核素。以 GeRa 计算代码为例，分析了当前水文地质建模软件的发展趋势。
{"title":"Status and Prospects for Development of Groundwater Flow and Transport Modeling Techniques to Address the Long-Term Radiation Safety Issues","authors":"I. V. Kapyrin","doi":"10.1134/s1066362223070019","DOIUrl":"https://doi.org/10.1134/s1066362223070019","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>The paper is focused on the problem of groundwater flow and transport modeling applied to safety assessment of nuclear facilities and development of relevant computational codes. The classification of typical tasks of the nuclear industry is provided, and specific features typical of different classes of simulated objects are analyzed, including their near and far fields. The most radioecologically relevant radionuclides are identified for each class. GeRa computational code is used as an example to analyze current trends of the development of hydrogeological modeling software.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140115168","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-03-12DOI: 10.1134/s1066362223070147
V. A. Remizova, P. A. Bobrov
Abstract
Alternative procedures for the dissolution of the solid phase (filter cake) of sludge formed by filtration of a spent nuclear fuel solution through cartridge and bulk filters were tested. Quite successful dissolution of the filter cake from the cartridge filter regeneration is ensured by successive treatment with alkali and acid solutions. Attempts to dissolve the filter cake from the bulk filter regeneration failed. The chemical and radiochemical composition of the filter cakes was evaluated. The results obtained will be used for assessing the nuclear and radiation safety and for developing procedures for the management of filter cakes from the filter regeneration.
{"title":"Determination of the Composition of the Filter Cake Formed by Filtration of Solutions from Reprocessing of Spent Nuclear Fuel of BN-600 Reactor","authors":"V. A. Remizova, P. A. Bobrov","doi":"10.1134/s1066362223070147","DOIUrl":"https://doi.org/10.1134/s1066362223070147","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>Alternative procedures for the dissolution of the solid phase (filter cake) of sludge formed by filtration of a spent nuclear fuel solution through cartridge and bulk filters were tested. Quite successful dissolution of the filter cake from the cartridge filter regeneration is ensured by successive treatment with alkali and acid solutions. Attempts to dissolve the filter cake from the bulk filter regeneration failed. The chemical and radiochemical composition of the filter cakes was evaluated. The results obtained will be used for assessing the nuclear and radiation safety and for developing procedures for the management of filter cakes from the filter regeneration.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140115480","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-03-12DOI: 10.1134/s1066362223070020
D. V. Markova, K. A. Feoktistov, P. V. Kozlov, O. M. Pankratova, S. V. Korenev, V. V. Milyutin, A. M. Egorin, E. A. Tokar’
Abstract
The radiation-chemical resistance of Fersal, RFR-i, RFR-Ca, and Clevasol sorbents was determined. The effect of the absorbed dose on the 137Cs distribution coefficient in sorption from an alkaline solution simulating the accumulated high-level waste solutions was studied. The sorbent samples were examined by electron microscopy. The mechanism of the degradation and oxidation of the sorbents on heating in air was determined.
{"title":"Radiation Resistance of Sorbents for Recovering Cesium from High-Level Alkaline Waste","authors":"D. V. Markova, K. A. Feoktistov, P. V. Kozlov, O. M. Pankratova, S. V. Korenev, V. V. Milyutin, A. M. Egorin, E. A. Tokar’","doi":"10.1134/s1066362223070020","DOIUrl":"https://doi.org/10.1134/s1066362223070020","url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>The radiation-chemical resistance of Fersal, RFR-i, RFR-Ca, and Clevasol sorbents was determined. The effect of the absorbed dose on the <sup>137</sup>Cs distribution coefficient in sorption from an alkaline solution simulating the accumulated high-level waste solutions was studied. The sorbent samples were examined by electron microscopy. The mechanism of the degradation and oxidation of the sorbents on heating in air was determined.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9,"publicationDate":"2024-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140115588","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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