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  1. No Access

    Article

    Extraction of plutonium(IV) from acidic feeds using several diamides with a tri-phenyl pyridine centre

    Three tri-aryl-pyridine (TAP) diamides containing a pyridine spacer were evaluated for the extraction of Pu(IV) and U(VI) using a process compatible diluent mixture of 95% dodecane + 5% isodecanol. Preferentia...

    M. Sivaramakrishna, D. R. Raut, S. K. Nayak… in Journal of Radioanalytical and Nuclear Che… (2019)

  2. No Access

    Article

    Extraction of \( {\text{Np}}^{4+} \) and \( {\text{NpO}}_{2}^{2+} \) from Nitric Acid Medium Using TODGA in Room Temperature Ionic Liquids

    Extraction of Np4+ and \( {\text{NpO}}_{2}^{2 + } \) ...

    S. A. Ansari, P. K. Mohapatra, D. R. Raut in Journal of Solution Chemistry (2018)

  3. No Access

    Article

    Evaluation of radiation resistance of hollow fibers for possible application in radioactive waste treatment

    Effect of gamma radiation on morphology, mechanical properties and hydrophobicity of hollow fibers made from different polymeric materials, such as poly ether–ether ketone with Card (PEEK-WC), polysulfone, pol...

    P. K. Mohapatra, S. A. Ansari, D. R. Raut… in Journal of Radioanalytical and Nuclear Che… (2017)

  4. No Access

    Article

    Simultaneous extraction of Cs and Sr from synthetic high level waste solutions using a solvent containing chlorinated dicarbollide and PEG-400 in PTMS

    A Cs selective solvent composed of 0.08 M chlorinated cobalt dicarbollide and 0.5 % PEG 400 (polyethylene glycol of average molecular weight of 400) in phenyl trifluoromethyl sulphone (PTMS) was used for the e...

    D. R. Raut, P. K. Mohapatra in Journal of Radioanalytical and Nuclear Chemistry (2014)

  5. No Access

    Article

    Radiation stability of several polymeric supports used for radionuclide transport from nuclear wastes using liquid membranes

    In an attempt to evaluate radiation stability of several polymeric materials used as the support in supported liquid membrane studies for the transport of radionuclides from nuclear waste, flat sheets made fro...

    P. K. Mohapatra, D. R. Raut, A. K. Ghosh… in Journal of Radioanalytical and Nuclear Che… (2013)

  6. No Access

    Article

    Characterization of high level waste for minor actinides by chemical separation and alpha spectrometry

    The high level waste (HLW) generated from the reprocessing of the spent fuel of pressurized heavy water reactor has been characterized for the minor actinides. The radiation dose of the waste solution was redu...

    M. S. Murali, A. Bhattacharayya, D. R. Raut… in Journal of Radioanalytical and Nuclear Che… (2012)

  7. No Access

    Article

    Effect of irradiation on AMP based resins for cesium separation from HNO3 feed solutions: batch and column studies

    Three different resins containing ammonium molybdophosphate (AMP), viz. PMMA (polymethylmethacrylate) resin, composite AMP resin and ALIX (a bisphenol based resin), were evaluated for their irradiation stabili...

    D. R. Raut, P. K. Mohapatra, P. K. Wattal… in Journal of Radioanalytical and Nuclear Che… (2012)

  8. No Access

    Article

    Removal of Cs from simulated high-level waste solutions by extraction using chlorinated cobaltdicarbollide in a mixture of nitrobenzene and xylene

    Efficacy of chlorinated cobaltdicarbollide in a modified diluent, 20% nitrobenzene in xylene was tested for the extraction and recovery of Cs from simulated high-level waste (HLW) solutions generated from PHWR...

    M. S. Murali, D. R. Raut, D. R. Prabhu… in Journal of Radioanalytical and Nuclear Che… (2012)

  9. No Access

    Article

    Extraction chromatographic study on the separation of Am3+ and Eu3+ using ethyl-BTP as the extractant

    Ethyl-substituted bis-triazinylpyridine (Et-BTP), a nitrogen containing soft-donor extractant, was used in investigations pertaining to the separation of Am3+ and Eu3+ from dilute nitric acid feed solutions by ex...

    A. Bhattacharyya, P. K. Mohapatra, T. Gadly… in Journal of Radioanalytical and Nuclear Che… (2011)

  10. No Access

    Article

    Preferential extraction of 90Y from 90Sr using N,N,N′,N′-tetra-2-ethylhexyl diglycolamide (T2EHDGA) as the extractant

    N,N,N′,N′-tetra-2-ethylhexyldiglycolamide (T2EHDGA) has been used for the preferential extraction of 90Y from its mixture with 90Sr from HNO3 as well as HCl medium. The separation efficiencies have been found out...

    S. Dutta, P. K. Mohapatra, D. R. Raut… in Journal of Radioanalytical and Nuclear Che… (2011)