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1. Process Control in Spent Nuclear Fuel Reprocessing Using Multisensor Potentiometry

   Abstract

   A multisensor system for quantitative determination of minor actinides and other transuranic elements jointly with rare earth elements in...

   Yu. S. Savosina, M. S. Agafonova-Moroz in Radiochemistry

   Article 01 April 2023
   

2. Recovery of Palladium from Nitric Acid Solutions of Spent Nuclear Fuel Reprocessing

   Abstract

   The possibility of palladium recovery from nitric acid solutions simultaneously with the in situ synthesis of iron(III) hexacyanoferrate(II)...

   P. V. Davydova, Yu. I. Korneyko, ... Yu. L. Kretser in Radiochemistry

   Article 01 June 2022
   

3. Technology for Reprocessing Mother–Wash Solution after Crystallization Purification of Spent Nuclear Fuel from High Temperature Gas-Cooled Reactor

   Abstract

   The extractants diphenyl- N,N -dioctylcarbamoylmethylphosphine oxide and diphenyl- N,N -diisobutylcarbamoylmethylphosphine oxide for the SNF...

   L. I. Tkachenko, V. L. Vidanov, ... A. Yu. Shadrin in Radiochemistry

   Article 01 April 2024
   

4. Determination of the Composition of the Filter Cake Formed by Filtration of Solutions from Reprocessing of Spent Nuclear Fuel of BN-600 Reactor

   Abstract

   Alternative procedures for the dissolution of the solid phase (filter cake) of sludge formed by filtration of a spent nuclear fuel solution...

   V. A. Remizova, P. A. Bobrov in Radiochemistry

   Article 01 December 2023
   

5. Nitric Acid Corrosion Issues of Spent Fuel Nuclear Fuel Reprocessing Plants Materials

   The degradation of reprocessing materials to nitric acid corrosion in aqueous spent fuel nuclear reprocessing plants is an unwanted and serious...

   S. Ningshen, R. Priya, U. Kamachi Mudali in A Treatise on Corrosion Science, Engineering and Technology

   Chapter 2022
   

6. Absorption spectra of neptunium and plutonium in spent fuel reprocessing active test

   The recovery of neptunium and plutonium play an important role in the spent nuclear fuel reprocessing process. Neptunium and plutonium are multiple...

   Dingming Li, Yongshen Zhang, ... Guoxin Tian in Journal of Radioanalytical and Nuclear Chemistry

   Article 10 March 2023
   

7. Extraction Technology for Reprocessing U–Be Fuel Solutions

   Abstract

   The results of experiments are presented on testing the separation of uranium from U-Be nuclear fuel solutions by extraction. It was shown...

   V. I. Volk, L. V. Arseenkov, ... V. S. Ermolin in Radiochemistry

   Article 01 June 2022
   

8. Dissolution of Mixed Nitride Uranium-Plutonium Spent Nuclear Fuel

   Abstract

   Data were obtained on the dissolution of voloxidized mixed nitride uranium-plutonium spent nuclear fuel (MNUP SNF), the amount and elemental...

   V. N. Momotov, E. A. Erin, ... K. N. Dvoeglazov in Radiochemistry

   Article 01 June 2023
   

9. Tensioned metastable fluid detector sensing technology for multifarious-multiscale applications in the nuclear fuel cycle

   The nuclear fuel cycle presents formidable 10 ³⁰⁺ multiscale challenges for high-efficiency spectroscopic sensing of alpha-neutron-fission radiation...

   Rusi P. Taleyarkhan, David DiPrete in Journal of Radioanalytical and Nuclear Chemistry

   Article 15 June 2024
   

10. Application of supercritical CO₂ extraction technology in spent nuclear fuel reprocessing

    Supercritical fluid extraction technology for metal complexes is a novel and green technology for extracting lanthanides and actinides from...

    Baoquan Qiao, Peng Lin, ... **ajie Liu in Journal of Radioanalytical and Nuclear Chemistry

    Article 01 December 2021
    

11. Development of U–Be Nuclear Fuel Dissolution Modes

    Abstract

    The results of experiments on development of dissolution modes of the uranium–beryllium nuclear fuel produced on an enlarged batch of...

    L. V. Arseenkov, A. M. Safiulina, ... V. S. Ermolin in Radiochemistry

    Article 01 June 2022
    

12. Voloxidation of Mixed Nitride Uranium–Plutonium Spent Nuclear Fuel

    Abstract

    The efficiency of voloxidation of mixed nitride uranium–plutonium spent nuclear fuel (MNUP SNF) for the separation of the fuel composition...

    V. N. Momotov, A. O. Makarov, ... K. N. Dvoeglazov in Radiochemistry

    Article Open access 01 April 2023
    

13. Assessment of Applicability of Bentonite Clay-Based Ceramics for Immobilization of Radioactive Waste from Pyrochemical Processing of Spent Nuclear Fuel

    Abstract

    The applicability of bentonite clay-based ceramics for immobilization of waste from pyrochemical reprocessing of spent nuclear fuel–spent...

    S. S. Poglyad, O. S. Dmitrieva, ... O. V. Romanova in Radiochemistry

    Article 01 December 2023
    

14. Assessment of Radioecologically Relevant Radionuclides ¹⁴C, ⁹⁹Tc, and ¹²⁹I in Vitrified High-Level Nuclear Wastes from Spent Fuel Reprocessing

    Abstract

    A method is proposed for quantifying the specific activities of radioecologically significant radionuclides, including ¹⁴ C, ⁹⁹ Tc, and ¹²⁹ I,...

    E. V. Chukhlantseva, O. V. Stepanova, ... P. A. Blokhin in Journal of Analytical Chemistry

    Article 01 December 2023
    

15. Effect of High-temperature VVER-1000 SNF Reprocessing Time on the Extent of Fission Product Removal

    Abstract

    Experiments on high-temperature reprocessing of VVER-1000 SNF with a burnout depth of 47 GW day/t U were carried out in order to determine...

    I. N. Skrigan, M. M. Metalidi, ... R. A. Serebryanskikh in Radiochemistry

    Article 01 April 2024
    

16. Spatial variation of radioiodine (¹²⁹I) dissolution from sediment of a brackish lake beside a spent nuclear fuel reprocessing plant in Japan

    The dissolution and chemical forms of sedimentary radioiodine ( ¹²⁹ I) in aquatic sediments were evaluated in Lake Obuchi, which is situated adjacent...

    Yuhi Satoh, Shoko Imai, Shinji Ueda in Journal of Radioanalytical and Nuclear Chemistry

    Article 10 July 2021
    

17. Experimental Modeling of Technetium(VII) Recovery from Raffinates after Extractive Reprocessing of Spent Nuclear Fuel

    Abstract

    Experimental justification has been provided for the possibility of extractive isolation of technetium from raffinate of technical process of...

    A. M. Safiulina, A. V. Anan’ev, ... K. N. Dvoeglazov in Russian Journal of Inorganic Chemistry

    Article 15 December 2020
    

18. Dissolution of Spent Nuclear Fuel Samples for Analytical Purposes

    Abstract

    The methods and procedures of dissolution employed in the conduct of radiochemical and elemental analyzes of spent nuclear fuel (SNF) were...

    V. N. Momotov, E. A. Erin, D. E. Tikhonova in Radiochemistry

    Article 01 October 2022

19. Nuclear Energy: Ion-Exchange Sorbents for Solving Environmental Protection Problems

    The status of nuclear power plants in the world is analyzed. Trends in the development of nuclear power in several countries are identified. Many...

    S. S. Yanchenko, A. Yu. Kuznetsov, ... A. A. Lysenko in Fibre Chemistry

    Article 01 September 2023

20. Extraction of uranyl from spent nuclear fuel wastewater via complexation—a local vibrational mode study

    Context

    The efficient extraction of uranyl from spent nuclear fuel wastewater for subsequent reprocessing and reuse is an essential effort toward...

    Bárbara M. T. C. Peluzo, Renaldo T. Moura Jr., Elfi Kraka in Journal of Molecular Modeling

    Article Open access 18 June 2024