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Yulia Mischenko

affiliation not provided to SSRN

  • affiliation not provided to SSRN

SCHOLARLY PAPERS

3

DOWNLOADS

164

TOTAL CITATIONS

3

Scholarly Papers (3)

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1.

U(X)N-Based Simfuel with X= Zr, Nb, Mo, and Ru: Fission Product Solubility and Speciation

Number of pages: 27 Posted: 11 Oct 2024
Jennifer Stansby, Denise Adorno-Lopes, Faris Sweidan, Yulia Mischenko, Melody Ranger, Mikael Jolkkonen, Vanessa K. Peterson, Edward G. Obbard and Pär Olsson
University of New South Wales (UNSW) - School of Mechanical and Manufacturing Engineering, Government of the United States of America - Oak Ridge National Laboratory, KTH Royal Institute of Technology, affiliation not provided to SSRN, affiliation not provided to SSRN, KTH Royal Institute of Technology, Government of the Commonwealth of Australia - Australian Nuclear Science and Technology Organisation, University of New South Wales (UNSW) - School of Mechanical and Manufacturing Engineering and Royal Institute of Technology (KTH)
Downloads 60 (970,490)

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Uranium nitride, fission products, SIMFUEL, phase identification, neutron diffraction, TAF-ID

2.

Enhanced Steam Oxidation Resistance of Uranium Nitride Nuclear Fuel Pellets

Number of pages: 22 Posted: 19 Sep 2023
Jennifer Stansby, Yulia Mischenko, Sobhan Patnaik, Vanessa K. Peterson, Christopher Baldwin, Patrick A. Burr, Denise Adorno-Lopes and Edward G. Obbard
University of New South Wales (UNSW) - School of Mechanical and Manufacturing Engineering, affiliation not provided to SSRN, affiliation not provided to SSRN, Government of the Commonwealth of Australia - Australian Nuclear Science and Technology Organisation, Government of the Commonwealth of Australia - Australian Nuclear Science and Technology Organisation, University of New South Wales (UNSW) - School of Mechanical and Manufacturing Engineering, affiliation not provided to SSRN and University of New South Wales (UNSW) - School of Mechanical and Manufacturing Engineering
Downloads 59 (970,490)
Citation 3

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ceramic, Weight loss, Oxidation, High temperature Corrosion, Kinetic parameters, Reactor conditions

3.

Accelerated and Heterogeneous Corrosion of Cr-Doped Uranium Nitride Fuel Pellets

Number of pages: 14 Posted: 27 Jan 2025
Jennifer Stansby, Yulia Mischenko, Sobhan Patnaik, Vanessa K. Peterson, Patrick A. Burr, Denise Adorno-Lopes and Edward G. Obbard
University of New South Wales (UNSW) - School of Mechanical and Manufacturing Engineering, affiliation not provided to SSRN, affiliation not provided to SSRN, Government of the Commonwealth of Australia - Australian Nuclear Science and Technology Organisation, University of New South Wales (UNSW) - School of Mechanical and Manufacturing Engineering, Government of the United States of America - Oak Ridge National Laboratory and University of New South Wales (UNSW) - School of Mechanical and Manufacturing Engineering
Downloads 45 (1,121,190)

Abstract:

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Uranium nitride, chromium, in situ, steam oxidation, neutron diffraction, biphasic