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Effect of Elevated Temperatures on the Dehydration of Radioactive Cement-Based Waste Forms Including Iron Hydroxide Slurries Containing α-Emitters 高温对含α-排放物的含氢氧化铁的放射性水泥基废物脱水的影响
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S106636222406016X
V. A. Remizova, P. A. Bobrov
{"title":"Effect of Elevated Temperatures on the Dehydration of Radioactive Cement-Based Waste Forms Including Iron Hydroxide Slurries Containing α-Emitters","authors":"V. A. Remizova,&nbsp;P. A. Bobrov","doi":"10.1134/S106636222406016X","DOIUrl":"10.1134/S106636222406016X","url":null,"abstract":"<p>The mechanical strength and chemical stability of the radioactive cement waste forms obtained by solidification of iron hydroxide slurries containing α-emitters were assessed with the aim to evaluate the effect of elevated temperatures in the range from 150 to 250°С. The dehydration of the waste forms in this temperature range exerts no significant negative effect on the extent of fixation of the radionuclides in the matrices and on the strength characteristics of the waste forms. The water loss on heating to 150°C is 11–13%, and further heating to 250°С leads to no more than 10% additional water loss.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"910 - 917"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143430959","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}
引用次数: 0
Solidification of the Strip Solution with Cesium-137 Using Porous Inorganic Material “Gubka” 多孔无机材料“Gubka”固化铯-137带材溶液
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060092
A. S. Aloy, A. N. Vizniy, T. I. Koltsova, D. N. Shishkin
{"title":"Solidification of the Strip Solution with Cesium-137 Using Porous Inorganic Material “Gubka”","authors":"A. S. Aloy,&nbsp;A. N. Vizniy,&nbsp;T. I. Koltsova,&nbsp;D. N. Shishkin","doi":"10.1134/S1066362224060092","DOIUrl":"10.1134/S1066362224060092","url":null,"abstract":"<p>At the Khlopin Radium Institute, during the development of extractive partitioning of the liquid high-level radioactive waste (HLW), a strip solution containing up to 6.0 × 10<sup>11</sup> Bq/dm<sup>3</sup> (16.3 Ci/dm<sup>3</sup>) of <sup>137</sup>Cs in the form of a nitric acid solution was collected and temporary was stored. To solidify this solution, a batch process using Gubka (sponge) porous inorganic material (PIM) was developed and implemented. Since that time, about 18 dm<sup>3</sup> of HLW was solidified into 12 sets of Gubka, reducing the liquid HLW volume by a factor of about 50. Gubka sets were placed into special containers, which after sealing by welding were delivered to the long-time storage of the RosRAO Branch in Sosnovy Bor.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"852 - 857"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143431007","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}
引用次数: 0
High-Entropy Melt of Lithium, Sodium, and Potassium Fluorides and Chlorides as a Possible Coolant for Molten-Salt Reactors 作为熔盐反应堆可能的冷却剂的高熵熔体的锂、钠、氟化钾和氯化物
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060031
D. O. Zakiryanov, N. K. Tkachev
{"title":"High-Entropy Melt of Lithium, Sodium, and Potassium Fluorides and Chlorides as a Possible Coolant for Molten-Salt Reactors","authors":"D. O. Zakiryanov,&nbsp;N. K. Tkachev","doi":"10.1134/S1066362224060031","DOIUrl":"10.1134/S1066362224060031","url":null,"abstract":"<p>Suggestions are made for potentially promising coolants for molten salt reactors from a mixture of six lithium, sodium, and potassium fluoride and chloride salts having high entropy of mixing. These compositions, which contain less lithium salts, should have higher thermodynamic stability than FLiNaK or FLiBe because of their high entropy. The chemical formula of the maximum high-entropy solution, Li<sub>1/6</sub>Na<sub>1/6</sub>K<sub>1/6</sub>F<sub>1/4</sub>Cl<sub>1/4</sub>, may result from mixing the variety of alkali halides like MX (M = Li, Na, K and X = F, Cl) taken in an equimolar ratio. Molecular dynamic estimations of the density, heat conductivity, and viscosity demonstrate reasonable values of these properties between those of the fluorides and chlorides.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"805 - 809"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143430909","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}
引用次数: 0
A Sorbent Based on Prefilter Resin Impregnated with 2-Ethylhexyl Hydrogen 2-Ethylhexylphosphonate for Extraction-Chromatographic Separation of Lanthanides 2-乙基己基磷酸氢浸渍预滤树脂萃取-色谱分离镧系元素
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060067
K. S. Bobrovskaya, R. A. Kuznetsov, M. N. Lisova, A. N. Fomin
{"title":"A Sorbent Based on Prefilter Resin Impregnated with 2-Ethylhexyl Hydrogen 2-Ethylhexylphosphonate for Extraction-Chromatographic Separation of Lanthanides","authors":"K. S. Bobrovskaya,&nbsp;R. A. Kuznetsov,&nbsp;M. N. Lisova,&nbsp;A. N. Fomin","doi":"10.1134/S1066362224060067","DOIUrl":"10.1134/S1066362224060067","url":null,"abstract":"<p>The characteristics of an extraction-chromatographic sorbent for lanthanide separation, prepared by impregnation of Prefilter resin with 2-ethylhexyl hydrogen 2-ethylhexylphosphonate, were studied. As demonstrated by the example of the Yb/Lu separation, in sorption from nitric acid solutions ([HNO<sub>3</sub>] &lt; 4 M) under batch conditions, the logarithm of the lanthanide distribution ratio is a linear function of the solution acidity. In column experiments, the flow rate of the mobile phase exerts the strong influence on the Yb/Lu separation efficiency. The temperature and sorbent particle size exert weaker influence. The characteristics of the suggested sorbent are identical to those of its analog, LN2 sorbent (EiChrom, USA). The sorbent based on Prefilter resin ensures lower, compared to LN2, extractant leaching.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"824 - 834"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143430960","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}
引用次数: 0
Preparation of a Nanodiamond Suspension with Immobilized Scandium Isotopes for in vivo Studies 固定化钪同位素纳米金刚石悬浮液的制备及体内研究
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060110
A. G. Kazakov, D. V. Pavlova, I. A. Ushakov, E. A. Nesterov, V. S. Skuridin, E. A. Odintsova, S. E. Vinokurov, B. F. Myasoedov
{"title":"Preparation of a Nanodiamond Suspension with Immobilized Scandium Isotopes for in vivo Studies","authors":"A. G. Kazakov,&nbsp;D. V. Pavlova,&nbsp;I. A. Ushakov,&nbsp;E. A. Nesterov,&nbsp;V. S. Skuridin,&nbsp;E. A. Odintsova,&nbsp;S. E. Vinokurov,&nbsp;B. F. Myasoedov","doi":"10.1134/S1066362224060110","DOIUrl":"10.1134/S1066362224060110","url":null,"abstract":"<p>Conditions were determined for preparing a suspension of detonation synthesis nanodiamonds (NDs) with immobilized scandium in solutions, meeting the requirements to solutions for intravenous administration of radiopharmaceuticals based on the medicinal isotopes <sup>44</sup>Sc and <sup>47</sup>Sc. The possibility of the quantitative binding of scandium with ND samples in isotonic solutions having the required pH and containing the minimal ND amount was demonstrated. The Freundlich and Langmuir adsorption isotherm parameters and Δ<i>G</i> of adsorption were determined for the most promising ND sample under the optimum conditions. The conditions found for preparing NDs with immobilized scandium isotopes will allow in vivo studies in the future.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"869 - 875"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1134/S1066362224060110.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143430961","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Extraction of REE(III) and Am(III) from a Nitric Acid Solution with Fe(III) and Mn(II) Dibutyl Phosphoric Acid Compounds 铁（III）和锰（II）二丁基磷酸化合物从硝酸溶液中萃取稀土（III）和镅(III
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060043
D. N. Shishkin, N. D. Goletskii
{"title":"Extraction of REE(III) and Am(III) from a Nitric Acid Solution with Fe(III) and Mn(II) Dibutyl Phosphoric Acid Compounds","authors":"D. N. Shishkin,&nbsp;N. D. Goletskii","doi":"10.1134/S1066362224060043","DOIUrl":"10.1134/S1066362224060043","url":null,"abstract":"<p>The behavior of a number of REE and Am(III) during their extraction from nitric acid solutions with iron and manganese dibutyl phosphoric acid (HDBP) compounds in various diluents was studied. An increase in the concentration of iron and manganese in the organic phase leads to an increase in the REE distribution ratios and, in some cases, to a noticeable change in the element separation factors. The element separation factors significantly differ depending on the diluent. The increase in the separation factors of pairs of elements can reach high values. For example, the Er/Dy separation factor in toluene increases by a factor of 5, and the Dy/Tb separation factor in chloroform, by a factor of 7. The use of decalin as a diluent leads in most cases to a maximum increase in the REE distribution ratios. In the system with an <i>o</i>-nitrotoluene (ONT) diluent, at a certain ratio of HDBP to Fe(III), the separation factors of americium and REE (except cerium) are high enough to allow their separation. The influence of the transition metal and solvent on the distribution and separation of REE is discussed.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"810 - 816"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143431005","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}
引用次数: 0
Fabrication and Characterization of (U,Pu)O2 Ceramic Fuel Pellets from Powders after Thermochemical Denitration of Nitric Acid Solutions 硝酸溶液热化学脱硝粉末制备（U,Pu）O2陶瓷燃料球团及其表征
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S106636222406002X
A. S. Aloy, K. Yu. Vergazov, M. V. Gorbachev, A. V. Davydov, R. V. Ismailov, V. A. Orlova, R. A. Serebryanskikh
{"title":"Fabrication and Characterization of (U,Pu)O2 Ceramic Fuel Pellets from Powders after Thermochemical Denitration of Nitric Acid Solutions","authors":"A. S. Aloy,&nbsp;K. Yu. Vergazov,&nbsp;M. V. Gorbachev,&nbsp;A. V. Davydov,&nbsp;R. V. Ismailov,&nbsp;V. A. Orlova,&nbsp;R. A. Serebryanskikh","doi":"10.1134/S106636222406002X","DOIUrl":"10.1134/S106636222406002X","url":null,"abstract":"<p>Thermochemical denitration of nitric acid solutions of U and Pu to obtain mixed uranium–plutonium formates was performed. It was followed by the reduction of the mixture in Ar–H<sub>2</sub> (5 vol %) to obtain a powder of mixed U–Pu dioxide. The products obtained were studied and characterized by X-ray diffraction, X-ray fluorescence analysis, and Raman spectroscopy. The analysis of the powder revealed the formation of a (U,Pu)O<sub>2</sub> solid solution containing 5 wt % Pu and of UO<sub>2</sub>. After the powder treatment by vortex mixing, high-density pellets of homogeneous structure were fabricated.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"796 - 804"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143431006","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}
引用次数: 0
Extraction of Ytterbium from Nitric Acid Solutions with Solutions of 2-Ethylhexyl Hydrogen 2-Ethylhexylphosphonate in Hexane 用2-乙基己基磷酸2-乙基己基氢溶液萃取硝酸溶液中的镱
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060079
K. S. Bobrovskaya, R. A. Kuznetsov
{"title":"Extraction of Ytterbium from Nitric Acid Solutions with Solutions of 2-Ethylhexyl Hydrogen 2-Ethylhexylphosphonate in Hexane","authors":"K. S. Bobrovskaya,&nbsp;R. A. Kuznetsov","doi":"10.1134/S1066362224060079","DOIUrl":"10.1134/S1066362224060079","url":null,"abstract":"<p>The extraction of ytterbium from nitric acid solutions with solutions of 2-ethylhexyl hydrogen 2-ethylhexylphosphonate (HEH[EHP]) in hexane was studied. The HEH[EHP] concentration was varied from 0.5 to 2.0 M; acidity, from 0.1 to 2.0 M; and lanthanide concentration, from 0.1 to 5 g/L. The dependences of the ytterbium distribution ratio on the solution acidity are described by equations of the type log <i>D = a </i>log[H<sup>+</sup>] + <i>b</i>, where the coefficient <i>a</i> depends on the extractant and lanthanide concentrations and varies from –1.26 to –3.0. Its variation is probably caused by the occurrence of the extraction by both cation-exchange and solvation mechanism. The model describing the dependence of the ytterbium distribution ratio on its concentration in the aqueous phase at different concentrations of the extractant and acid was suggested. The data predicted by the model reasonably agree with the experimental data.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"835 - 845"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143431008","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}
引用次数: 0
Sorption of Tetravalent Actinides from Nitric Acid Process Solutions Using Anion-Exchange Resins Produced by Smoly Group of Enterprises 用斯莫里集团生产的阴离子交换树脂吸附硝酸工艺溶液中的四价锕系元素
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060080
E. V. Lyzlova, A. V. Glukhova, L. V. Chernavskaya, A. V. Konnikov, M. S. Lysenko
{"title":"Sorption of Tetravalent Actinides from Nitric Acid Process Solutions Using Anion-Exchange Resins Produced by Smoly Group of Enterprises","authors":"E. V. Lyzlova,&nbsp;A. V. Glukhova,&nbsp;L. V. Chernavskaya,&nbsp;A. V. Konnikov,&nbsp;M. S. Lysenko","doi":"10.1134/S1066362224060080","DOIUrl":"10.1134/S1066362224060080","url":null,"abstract":"<p>The possibility of using new anion-exchange resins AM-4VP, AM_pu, AMP-p, AM-p, and AM-2B produced by Smoly Group of Enterprises for plutonium recovery from nitric acid process solutions was examined. The physicochemical characteristics of the resins, the thorium distribution coefficients as functions of the nitric acid concentration, and the static exchange capacities of the resins were determined. The plutonium recovery from process solutions was studied in column experiments. The physicochemical properties and sorption ability of the anion-exchange resins were compared to those of the previously used VP-1Ap resin. AM-4VP resin shows promise for plutonium recovery from nitric acid process solutions.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"846 - 851"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143431009","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}
引用次数: 0
Experimental Check of the Suitability of an Iron Phosphate Ceramic for Immobilization of Radioactive Waste from Pyrochemical Reprocessing of Spent Nuclear Fuel 磷酸铁陶瓷固定乏燃料热化学后处理放射性废物的适用性实验研究
IF 0.9
Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060134
S. S. Poglyad, Ya. I. Shatalina, E. A. Bezdnyakova, O. S. Dmitrieva
{"title":"Experimental Check of the Suitability of an Iron Phosphate Ceramic for Immobilization of Radioactive Waste from Pyrochemical Reprocessing of Spent Nuclear Fuel","authors":"S. S. Poglyad,&nbsp;Ya. I. Shatalina,&nbsp;E. A. Bezdnyakova,&nbsp;O. S. Dmitrieva","doi":"10.1134/S1066362224060134","DOIUrl":"10.1134/S1066362224060134","url":null,"abstract":"<p>The suitability of a matrix based on an iron phosphate ceramic (IPC) for immobilization of waste from pyrochemical reprocessing of spent nuclear fuel (spent electrolyte, a readily water-soluble fusion cake of alkali metal chlorides) was examined. The phase composition, chemical durability, and mechanical strength of the matrix material were studied. The matrix meets the requirements to a cement compound formulated in NP-019-15 regulation document and is suitable for radioactive waste disposal.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"882 - 889"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143430963","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}
引用次数: 0
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