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    Depletion Calculations for an Integral Small Molten Salt Reactor With Serpent

    Source: Journal of Nuclear Engineering and Radiation Science:;2023:;volume( 010 ):;issue: 002::page 21301-1
    Author:
    Wang, Xiaolin
    ,
    Nguyen, T. Sinh
    ,
    Wojtaszek, Daniel
    DOI: 10.1115/1.4063111
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The molten salt reactor (MSR) concept is among the Generation IV designs considered feasible for providing clean, safe, sustainable, and economical energy supplies to the world's population. The depletion of fuel for a small modular fluoride molten salt reactor (sm-FMSR) with a closed fuel cycle based on the integral molten salt reactor concept has been investigated using Serpent. The Monte Carlo transport code Serpent has burnup capability and flow features that can be used to model fuel circulation and online fuel addition in an MSR. Three fueling schemes to control Serpent depletion cycles have been simulated and compared: step fueling (SF), continuous fueling with all fission products (FPs) accumulating in the reactor system (CFA), and continuous fueling with insoluble FPs separated from fuel (CFS). CFA and CFS require fewer depletion cycles that are longer in duration than the cycles required by SF, in order to maintain the effective multiplication factor (keff) within a working range over the seven years of the reactor fuel cycle. sm-FMSRs with SF and with CFA require similar quantities of “top-up” fuel, consume similar fuel (fissile) amounts, and result in similar fuel isotopic concentrations if keff is kept within a similar range. However, with separation of insoluble FPs from the circulating fuel, CFS gains a large reactivity worth due to the removal of FP poisons. This allows for reduction of fuel enrichment in both initial and total top-up fuel and leads to savings of a considerable fissile quantity in fueling MSR and in spent fuel. The Serpent depletion calculations require manual arithmetic calculations for adjustment of the Serpent built-in settings before the start of every calculation cycle for all three fueling schemes. Implementation of additional Serpent flow features in changing material volumes and flow constants would facilitate the simulation of the fuel depletion process and allow for more realistic simulations of fuel circulation.
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      Depletion Calculations for an Integral Small Molten Salt Reactor With Serpent

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4295738
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorWang, Xiaolin
    contributor authorNguyen, T. Sinh
    contributor authorWojtaszek, Daniel
    date accessioned2024-04-24T22:42:57Z
    date available2024-04-24T22:42:57Z
    date copyright10/20/2023 12:00:00 AM
    date issued2023
    identifier issn2332-8983
    identifier otherners_010_02_021301.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4295738
    description abstractThe molten salt reactor (MSR) concept is among the Generation IV designs considered feasible for providing clean, safe, sustainable, and economical energy supplies to the world's population. The depletion of fuel for a small modular fluoride molten salt reactor (sm-FMSR) with a closed fuel cycle based on the integral molten salt reactor concept has been investigated using Serpent. The Monte Carlo transport code Serpent has burnup capability and flow features that can be used to model fuel circulation and online fuel addition in an MSR. Three fueling schemes to control Serpent depletion cycles have been simulated and compared: step fueling (SF), continuous fueling with all fission products (FPs) accumulating in the reactor system (CFA), and continuous fueling with insoluble FPs separated from fuel (CFS). CFA and CFS require fewer depletion cycles that are longer in duration than the cycles required by SF, in order to maintain the effective multiplication factor (keff) within a working range over the seven years of the reactor fuel cycle. sm-FMSRs with SF and with CFA require similar quantities of “top-up” fuel, consume similar fuel (fissile) amounts, and result in similar fuel isotopic concentrations if keff is kept within a similar range. However, with separation of insoluble FPs from the circulating fuel, CFS gains a large reactivity worth due to the removal of FP poisons. This allows for reduction of fuel enrichment in both initial and total top-up fuel and leads to savings of a considerable fissile quantity in fueling MSR and in spent fuel. The Serpent depletion calculations require manual arithmetic calculations for adjustment of the Serpent built-in settings before the start of every calculation cycle for all three fueling schemes. Implementation of additional Serpent flow features in changing material volumes and flow constants would facilitate the simulation of the fuel depletion process and allow for more realistic simulations of fuel circulation.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleDepletion Calculations for an Integral Small Molten Salt Reactor With Serpent
    typeJournal Paper
    journal volume10
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4063111
    journal fristpage21301-1
    journal lastpage21301-7
    page7
    treeJournal of Nuclear Engineering and Radiation Science:;2023:;volume( 010 ):;issue: 002
    contenttypeFulltext
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