Radiation Physics and Engineering
A peer-reviewed journal published by K. N. Toosi University of Technology

Neutronic simulation, analyses, and performance evaluation of a very small Micro Modular Reactor (MMR) called MARVEL versus different advanced nuclear fuel types using MCNP6

Document Type : Research Article

Authors

Vahid Moradi 1
Mohammad Hossein Estaki 1
Afshin Hedayat 2

1 Department of Nuclear Engineering, Faculty of Physics, University of Isfahan, Hezarjarib Avenue, Postal Code: 81746-73441, Isfahan, Iran

2 Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute (NSTRI), End of North Karegar Street, Postal Code: 14399-51113 Tehran, Iran

https://doi.org/10.22034/rpe.2024.487009.1254
Abstract
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, UO2, 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.

Highlights

  • Developing simulation and analyses of a very high-tech and state-of-the-art MMR.
  • Performing accurate neutronic simulation in detail using MCNP6.
  • Providing a comparison study between four different advanced fuel types.
  • Coming up with more innovations towards industrial or practical applications.
  • Enhancing both neutronic and safety parameters practically and coherently.

Keywords

MARVEL
MMR
Neutronic Analyses
MCNP
Nuclear Fuel
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Radiation Physics and Engineering
Volume 6, Issue 3
Spring 2025
Pages 17-26

  • Receive Date 04 November 2024
  • Revise Date 08 December 2024
  • Accept Date 24 December 2024

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