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Home » Archive of journals » 2026, ¹ 2 (35) » Development and testing of a comprehensive process flow chart for the extraction of a short-lived cesium-strontium fraction from HLW resulting from NPP SNF reprocessing and its solidification involving glass compound pilot sample production and certification

DEVELOPMENT AND TESTING OF A COMPREHENSIVE PROCESS FLOW CHART FOR THE EXTRACTION OF A SHORT-LIVED CESIUM-STRONTIUM FRACTION FROM HLW RESULTING FROM NPP SNF REPROCESSING AND ITS SOLIDIFICATION INVOLVING GLASS COMPOUND PILOT SAMPLE PRODUCTION AND CERTIFICATION

JOURNAL: 2026, ¹ 2 (35), p. 63-74

AUTHORS: A.I. Shirokov, Y.A. Voroshilov, A.V. Konnikov, P.V. Kozlov, E.V. Polyakov, E.V. Chukhlantseva, S.A. Lukin, M.V. Logunov, V.P. Borisenko, S.M. Chadov, A.V. Sheremetyev

ANNOTATION:

The study considers a package of methods developed and tested as part of the new Sustainable Nuclear Fuel Cycle
(SNFC) product line providing the extraction of the short-lived cesium-strontium fraction (SF) concentrate from high-level
waste (HLW) resulted from spent nuclear fuel (SNF) reprocessing, its treatment and solidifi ation. The operations
were conducted at a pilot facility in a series of hot cells of the RT-1 plant at PA Mayak. Dynamic extraction method
with crown ethers was used to effectively separate the cesium-strontium fraction. Refining sorption treatment o the
cesium and strontium re-extract from minor actinides and other long-lived contaminants was performed. The study
yielded a borosilicate glass composition providing reliable isolation of the SF enabling its long-term storage. Pilot
samples of highly active glass with varying inclusions of cesium-strontium fractions have been manufactured. A package
of analytical control methods has been developed based on which the composition of the SF concentrate can be
evaluated and the glass compound can be certified One of the pilot samples was studied and it was found that its
characteristics were meeting all the SNFC requirements. Thus, it was demonstrated that the compound containing SF
no longer required disposal in deep geological formations upon its return to the international customer.


Keywords: sustainable nuclear fuel cycle, high-level waste, short-lived fraction, extraction, crown ether, cesium, strontium,
actinides, borosilicate glass, monitored radionuclides, radioactive waste.


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Shirokov A. I., Voroshilov Yu. A., Konnikov A. V., Kozlov P. V., Polyakov E. V., Chukhlantseva E. V., Lukin S. A., Logunov M. V., Borisenko V. P., Chadov S. M., Sheremetyev A. V. Development and Testing of a Comprehensive Process Flow Chart for the Extraction of a Short-Lived Cesium-Strontium Fraction from HLW Resulting from NPP SNF Reprocessing and its Solidification Involving Glass Compound Pilot Sample Production and Certification Radioactive Waste, 2026, no. 2 (35), pp. 63—74. DOI: 10.25283/258 -9707-2026-2-63-74 (In Russian).


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