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  1. Article

    Open Access

    Aggregation behaviour of radiolytically degraded diglycolamide based solvent system

    The 0.1 M TODGA + 0.2 M DOHyA/n-DD phase was irradiated to various absorbed dose levels and the extraction behaviour of nitric acid and Nd(III) in the irradiated organic phases were studied. The organic phase was...

    N. Parvathy, Jammu Ravi, N. Desigan… in Journal of Radioanalytical and Nuclear Che… (2024)

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  2. No Access

    Article

    Feasibility of using the mixture of two symmetrical diglycolamides instead of unsymmetrical diglycolamide solvent for the separation of trivalent actinides

    A mixture of 0.05 M N,N,N’,N’-tetraoctyl diglycolamide (TODGA) + 0.05 M N,N,N’,N’-tetra-2-ethylhexyl diglycolamide (TEHDGA)/n-dodecane was evaluated for its resemblance with its corresponding unsymmetrical diglyc...

    Jammu Ravi, N. Parvathy, N. Desigan… in Journal of Radioanalytical and Nuclear Che… (2023)

  3. No Access

    Article

    Solvent wash studies for the removal of di-butyl phosphate from spent solvent under simulated PUREX condition

    Reprocessing of high plutonium content spent nuclear fuel from fast reactors results in the generation of lean organic solution containing considerably high amount of di-butyl phosphoric acid. Use of sodium ca...

    Satyabrata Mishra, P. Vishnu Anand… in Journal of Radioanalytical and Nuclear Che… (2023)

  4. No Access

    Article

    Kinetics of dissolution of simulated (U–Ce) MOX fuel pellet in nitric acid

    In the present study, the dissolution kinetics of simulated urania, ceria MOX fuel pellets in nitric acid under PUREX process condition has been investigated. Influence of various parameters like initial conce...

    Elizabeth Augustine, N. Desigan, R. Rajeev… in Journal of Radioanalytical and Nuclear Che… (2022)

  5. No Access

    Article

    Electrolytic and ozone aided destruction of oxalate ions in plutonium oxalate supernatant of the PUREX process: A comparative study

    The article describes an efficient and straight forward method for the destruction of oxalate ions in the plutonium oxalate supernatant stream generated during the reprocessing of FBTR spent fuel, using ozone ...

    S. Ganesh, N. Desigan, A. Chinnusamy… in Journal of Radioanalytical and Nuclear Che… (2021)

  6. No Access

    Article

    Effect of temperature, radiation dose and composition on density, viscosity and volumetric properties of N,N,N′,N′-tetraoctyl diglycolamide (TODGA) and n-dodecane mixture, a promising system for the separation of actinides

    The organic solution composed of N,N,N′,N′-tetraoctyldiglycolamide (TODGA) and n-dodecane is extensively studied for the removal of trivalent actinides from the high-level liquid waste arising from nuclear indust...

    Jammu Ravi, Satyabrata Mishra, Remya Murali… in Journal of Radioanalytical and Nuclear Che… (2021)

  7. No Access

    Article

    Analysis of kinetic data for the dissolution of UO2 fuel pellets in nitric acid

    In the present study, the dissolution kinetics of UO2 pellets in nitric acid has been investigated. Kinetic rate expressions based on Langmuir–Hinshelwood mechanism have been developed to describe the kinetics of...

    Elizabeth Augustine, N. Desigan… in Journal of Radioanalytical and Nuclear Che… (2020)

  8. No Access

    Article

    Mechanism of dissolution of nuclear fuel in nitric acid relevant to nuclear fuel reprocessing

    The mechanism of dissolution of sintered UO2 fuel pellets in nitric acid is the essential starting input information required for the design of a continuous dissolution system for spent nuclear fuel reprocessing....

    N. Desigan, Nirav P. Bhatt, N. K. Pandey… in Journal of Radioanalytical and Nuclear Che… (2017)