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    A Comparative Analysis of Mixing Performance of Power-Law Fluid in Cylindrical Microchannels With Sudden Contraction/Expansion 

    Source: Journal of Fluids Engineering:;2020:;volume( 142 ):;issue: 006
    Author(s): Banerjee, A.; Nayak, A. K.; Weigand, B.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper focuses on the comparative electrokinetic micromixing of non-Newtonian fluid in cylindrical microchannels with surface potential heterogeneity due to sudden constriction/expansion. In numerical simulations, the ...
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    Pressurized Heavy Water Reactor Technology: Its Relevance Today 

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 002:;page 20901
    Author(s): Nayak, A. K.; Banerjee, S.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The pressurized heavy water reactor (PHWR) technology was conceived in Canada and has moved to several nations for commercial production of electricity. Currently, 49 power reactors operate with PHWR technology producing ...
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    In-Calandria Retention of Corium in PHWR: Experimental Investigation and Remaining Issues 

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 002:;page 20909
    Author(s): Prasad, Sumit V.; Nayak, A. K.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: After the Fukushima accident, the public has expressed concern regarding the safety of nuclear power plants. This accident has strengthened the necessity for further improvement of safety in the design of existing and ...
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    Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration 

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 003:;page 31014
    Author(s): Prasad, Sumit V.; Nayak, A. K.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The present experimental investigation in a scaled facility of an Indian pressurized heavy water reactors (PHWRs) is focused on the heat transfer behavior from the calandria vessel (CV) to the calandria vault during a ...
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    Experimental Evaluation of Critical Heat Flux in Downward-Facing Boiling on SS304 L Flat Plate Relevant to In-Calandria Retention in PHWRs 

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 003
    Author(s): Prasad, Sumit V.; Nayak, A. K.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Retention of corium inside the calandria vessel (CV) by externally cooling it by calandria vault water is essential to mitigate severe accidents in pressurized heavy water reactor (PHWR). The thermal failure of CV can be ...
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    Enhanced Electro-Osmotic Flow of Power-Law Fluids in Hydrophilic Patterned Nanochannel 

    Source: Journal of Fluids Engineering:;2020:;volume( 142 ):;issue: 010:;page 0101201-1
    Author(s): Majhi, M.; Nayak, A. K.; Banerjee, A.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In this paper, electro-osmotic flow (EOF) enhancement of non-Newtonian power-law fluids in a modulated nanochannel with polarized wall is proposed. The channel walls are embedded with periodically arranged rectangular ...
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    Special Section: Pressurized Heavy Water Reactors Safety 

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 002:;page 20301
    Author(s): Banerjee, S.; Nayak, A. K.; Nitheanandan, T. (Nithy)
    Publisher: The American Society of Mechanical Engineers (ASME)
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    Numerical Investigations of the Effect of Radial Power Distribution and Inlet Orifice on the Stability Behavior of Parallel Multichannel Type Natural Circulation Boiling Water Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 003:;page 31002
    Author(s): Singh, Sapna; Singal, Garima; Nayak, A. K.; Kannan, Umasankari
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In a natural circulation boiling water reactor (BWR), the core power varies in both axial and radial directions inside the reactor core. The variation along the axial direction is more or less constant throughout the ...
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    Critical Heat Flux on Curved Calandria Vessel of Indian PHWRs During Severe Accident Condition 

    Source: Journal of Heat Transfer:;2020:;volume( 143 ):;issue: 002:;page 022101-1
    Author(s): Verma, P. K.; Kulkarni, P. P.; Pandey, P.; Prasad, S. V.; Nayak, A. K.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In pressurized heavy water reactors (PHWRs), during an unmitigated severe accident, the absence of adequate cooling arising from multiple failures of the cooling system leads to the collapse of pressure tubes and calandria ...
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    In-Vessel Retention of PHWRs: Experiments at Prototypic Temperatures 

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 001:;page 011601-1
    Author(s): Prasad, Sumit V.; Kulkarni, P. P.; Yadav, D. C.; Verma, P. K.; Nayak, A. K.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In pressurized heavy water reactors (PHWRs), multiple failures of engineered safety features may cause a failure of core cooling eventually leading to core collapse. The failed fuel and fuel channels relocate to the bottom ...
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