Search Results - Mallick, Amod Kishore

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  1. 1
    Analysis of Kobayashi benchmark with indigenous Monte Carlo neutron transport code PATMOC

    Analysis of Kobayashi benchmark with indigenous Monte Carlo neutron transport code PATMOC by Mallick, Amod Kishore, Kannan, Umasankari

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  2. 2
    Simulation of random medium of fuel pebble with liquid salt coolant using PebMC code

    Simulation of random medium of fuel pebble with liquid salt coolant using PebMC code by Singh, Indrajeet, Mallick, Amod Kishore, Gupta, Anurag, Kannan, Umasankari

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  3. 3
    Determination of spectrum shaping factor in nuclear reactor AHWR-CF by Monte Carlo method for material characterization using neutrons

    Determination of spectrum shaping factor in nuclear reactor AHWR-CF by Monte Carlo method for material characterization using neutrons by Bhandari, Deep, Kishore Mallick, Amod, Samanta, Sudipta, Sarkar, Anindita, Kumar, Rajeev, Kannan, Umasankari

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  4. 4
    Benchmarking exercise of indigenous Monte Carlo neutron transport code PATMOC for hexagonal full core reactor geometry

    Benchmarking exercise of indigenous Monte Carlo neutron transport code PATMOC for hexagonal full core reactor geometry by Mallick, Amod Kishore, Kannan, Umasankari

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  5. 5
    Sub-space iteration based Monte Carlo scheme for simultaneous computation of multiple dominant k-eigenmodes and acceleration of fission source iterations

    Sub-space iteration based Monte Carlo scheme for simultaneous computation of multiple dominant k-eigenmodes and acceleration of fission source iterations by Mallick, Amod Kishore, Gupta, Anurag

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  6. 6
    Investigation on the Use of the Monte Carlo Iterative k-Source Scheme for the Study of Neutron Subcritical Multiplication

    Investigation on the Use of the Monte Carlo Iterative k-Source Scheme for the Study of Neutron Subcritical Multiplication by Mallick, Amod Kishore, Gupta, Anurag, Kannan, Umasankari

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  7. 7
    A New Approach to Monte Carlo in High Temperature Reactors

    A New Approach to Monte Carlo in High Temperature Reactors by Singh, Indrajeet, Degweker, S. B., Mallick, Amod Kishore, Gupta, Anurag

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  8. 8
    Experimental study of voiding effects with thorium based MOX fuel cluster in Critical Facility

    Experimental study of voiding effects with thorium based MOX fuel cluster in Critical Facility by Mallick, Amod Kishore, Kumar, Rajeev, Samanta, Sudipta, Upreti, Yogesh, Deo, Kapil, Bhandari, Deep, Kannan, Umasankari, Shivakumar, V., Kumar Verma, Sharad, De, S.K., Sharma, Avaneesh

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  9. 9
    A Diffusion Monte Carlo-Based Algorithm for Estimation of Higher Modes of a Reactor

    A Diffusion Monte Carlo-Based Algorithm for Estimation of Higher Modes of a Reactor by Srivastava, Argala, Singh, K. P., Mallick, Amod Kishore, Kannan, Umasankari, Degweker, S. B.

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  10. 10
    Use of finite-difference diffusion Monte Carlo method to generate Shannon entropy of the fission distribution in a nuclear reactor core

    Use of finite-difference diffusion Monte Carlo method to generate Shannon entropy of the fission distribution in a nuclear reactor core by Srivastava, Argala, Mallick, Amod Kishore, Singh, K. P., Kannan, Umasankari

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