Neutronic simulation, analyses, and performance evaluation of a very small Micro Modular Reactor (MMR) called MARVEL versus different advanced nuclear fuel types using MCNP۶
محل انتشار: فصلنامه فیزیک و مهندسی پرتو، دوره: 6، شماره: 3
سال انتشار: 1404
نوع سند: مقاله ژورنالی
زبان: انگلیسی
مشاهده: 43
نسخه کامل این مقاله ارائه نشده است و در دسترس نمی باشد
- صدور گواهی نمایه سازی
- من نویسنده این مقاله هستم
استخراج به نرم افزارهای پژوهشی:
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.
کلیدواژه ها:
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
مراجع و منابع این مقاله:
لیست زیر مراجع و منابع استفاده شده در این مقاله را نمایش می دهد. این مراجع به صورت کاملا ماشینی و بر اساس هوش مصنوعی استخراج شده اند و لذا ممکن است دارای اشکالاتی باشند که به مرور زمان دقت استخراج این محتوا افزایش می یابد. مراجعی که مقالات مربوط به آنها در سیویلیکا نمایه شده و پیدا شده اند، به خود مقاله لینک شده اند :