Neutronic simulation, analyses, and performance evaluation of a very small Micro Modular Reactor (MMR) called MARVEL versus different advanced nuclear fuel types using MCNP۶

سال انتشار: 1404
نوع سند: مقاله ژورنالی
زبان: انگلیسی
مشاهده: 43

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شناسه ملی سند علمی:

JR_RPE-6-3_003

تاریخ نمایه سازی: 26 خرداد 1404

چکیده مقاله:

Some prominent and well-known companies or institutes recently developed a new Micro Modular Reactors (MMR) generation. Such a new design mainly includes the monolith core structure, heat pipes, Stirling engines, and very tiny or compact designs. MARVEL is one of the most miniature and innovative designs as well. Undoubtedly, such a compact and innovative design has a lot of strategic or multi-purpose applications. Despite their advantages and applications, each new design should be accurately analyzed and checked against different aspects. In this paper, MARVEL, one of the most advanced emerging technologies, is selected for neutronic simulations and in-depth analyses using MCNP. Moreover, the reactor core design is analyzed and evaluated by loading four advanced nuclear fuel types. They are UZRH, UO۲, Uranium Nitride, and MOX. Parameters include the effective multiplication factor, neutron flux distribution, power peaking factor, reactor kinetics, fuel burn up, and consumption. Results are quite promising in utilizing such advanced nuclear fuels for such an advanced compact reactor. Finally, each type may have its advantages and disadvantages as well.

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نویسندگان

Vahid Moradi

Department of Nuclear Engineering, Faculty of Physics, University of Isfahan, Hezarjarib Avenue, Postal Code: ۸۱۷۴۶-۷۳۴۴۱, Isfahan, Iran

Mohammad Hossein Estaki

Department of Nuclear Engineering, Faculty of Physics, University of Isfahan, Hezarjarib Avenue, Postal Code: ۸۱۷۴۶-۷۳۴۴۱, Isfahan, Iran

Afshin Hedayat

Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute (NSTRI), End of North Karegar Street, Postal Code: ۱۴۳۹۹-۵۱۱۱۳ Tehran, Iran

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