A Comparison of Deterministic and Monte Carlo Depletion Methods for HTGR Fuel Elements

M. DeHart, Jaakko Leppänen

    Research output: Contribution to journalArticleScientificpeer-review

    2 Citations (Scopus)

    Abstract

    Two independent methods using both deterministic and Monte Carlo methods are used to perform depletion calculations for a set of simple HTGR-type configurations, and are found to be in excellent agreement. The explicit representation of randomly dispersed particles used within a continuous energy Serpent solution represents the best estimate simulation of fuel particle interactions. The DH treatment in TRITON allows simulation of grain-to-grain effects without requiring the detailed representation of each individual grain, and is found to be in very close agreement with Serpent results. In absence of qualified experimental data for spent fuel samples burned in a prototypic environment, this very close agreement of completely independent methods and data provides a great deal of confidence in the capabilities of both methods to represent the physics of HTGR fuel depletion. Additional submissions of results for this benchmark from other organizations are expected, which will provide an even greater variety of methods and data for comparison. Compilation and comparison of results should provide considerable insight into strengths and limitations of various methods and data for HTGR analysis.
    Original languageEnglish
    Pages (from-to)778-781
    Number of pages4
    JournalTransactions of the American Nuclear Society
    Volume101
    Publication statusPublished - 2009
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    high temperature gas cooled reactors
    nuclear fuel elements
    depletion
    spent fuels
    particle interactions
    Monte Carlo method
    confidence
    simulation
    physics
    estimates
    configurations
    energy

    Cite this

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    abstract = "Two independent methods using both deterministic and Monte Carlo methods are used to perform depletion calculations for a set of simple HTGR-type configurations, and are found to be in excellent agreement. The explicit representation of randomly dispersed particles used within a continuous energy Serpent solution represents the best estimate simulation of fuel particle interactions. The DH treatment in TRITON allows simulation of grain-to-grain effects without requiring the detailed representation of each individual grain, and is found to be in very close agreement with Serpent results. In absence of qualified experimental data for spent fuel samples burned in a prototypic environment, this very close agreement of completely independent methods and data provides a great deal of confidence in the capabilities of both methods to represent the physics of HTGR fuel depletion. Additional submissions of results for this benchmark from other organizations are expected, which will provide an even greater variety of methods and data for comparison. Compilation and comparison of results should provide considerable insight into strengths and limitations of various methods and data for HTGR analysis.",
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    A Comparison of Deterministic and Monte Carlo Depletion Methods for HTGR Fuel Elements. / DeHart, M.; Leppänen, Jaakko.

    In: Transactions of the American Nuclear Society, Vol. 101, 2009, p. 778-781.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - A Comparison of Deterministic and Monte Carlo Depletion Methods for HTGR Fuel Elements

    AU - DeHart, M.

    AU - Leppänen, Jaakko

    PY - 2009

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    AB - Two independent methods using both deterministic and Monte Carlo methods are used to perform depletion calculations for a set of simple HTGR-type configurations, and are found to be in excellent agreement. The explicit representation of randomly dispersed particles used within a continuous energy Serpent solution represents the best estimate simulation of fuel particle interactions. The DH treatment in TRITON allows simulation of grain-to-grain effects without requiring the detailed representation of each individual grain, and is found to be in very close agreement with Serpent results. In absence of qualified experimental data for spent fuel samples burned in a prototypic environment, this very close agreement of completely independent methods and data provides a great deal of confidence in the capabilities of both methods to represent the physics of HTGR fuel depletion. Additional submissions of results for this benchmark from other organizations are expected, which will provide an even greater variety of methods and data for comparison. Compilation and comparison of results should provide considerable insight into strengths and limitations of various methods and data for HTGR analysis.

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    EP - 781

    JO - Transactions of the American Nuclear Society

    JF - Transactions of the American Nuclear Society

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