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Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core

Author

Listed:
  • Mohammad Alrwashdeh

    (Department of Nuclear Engineering, Emirates Nuclear Technology Center (ENTC), Khalifa University of Science and Technology, Abu Dhabi P.O. Box 127788, United Arab Emirates)

  • Saeed A. Alameri

    (Department of Nuclear Engineering, Emirates Nuclear Technology Center (ENTC), Khalifa University of Science and Technology, Abu Dhabi P.O. Box 127788, United Arab Emirates)

Abstract

The accident-tolerant fuel concept involves replacing the conventional cladding system (zirconium) with a new material or coating that has specific thermomechanical properties. The aim of this study is to evaluate the neutronics performance of a chromium coating concept and design solutions. A Zircaloy–uranium fuel system (Zr–U) is currently used as a standard fuel system in pressurized water reactors around the world. This investigation presents the benefits of utilizing an alternative cladding material such as chromium coating and the effects on the thermal neutron parameters of the way in which the chromium coating is introduced in the reactor fuel. Among these significant benefits is an increase in the reactor fuel’s thermal conductivity, which improves reactor safety. Two types of fuel-cladding systems were investigated: Zircaloy–uranium (Zr–U) and Zircaloy–chromium (Zr–Cr–U) coating fuel systems. Neutronics analysis evaluations were performed for the selected fuel assemblies and a two-dimensional full core based on an APR-1400 reactor design. Neutronics analyses were performed for the application of the new fuel-cladding material systems using the reactor-physics Monte Carlo code Serpent 2.31.

Suggested Citation

  • Mohammad Alrwashdeh & Saeed A. Alameri, 2022. "Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core," Energies, MDPI, vol. 15(21), pages 1-16, October.
    • Handle: RePEc:gam:jeners:v:15:y:2022:i:21:p:8008-:d:955779
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    References listed on IDEAS

    as
    1. Mohammad Alrwashdeh & Saeed A. Alameri, 2022. "SiC and FeCrAl as Potential Cladding Materials for APR-1400 Neutronic Analysis," Energies, MDPI, vol. 15(10), pages 1-17, May.
    2. Przemysław Stanisz & Mikołaj Oettingen & Jerzy Cetnar, 2022. "Development of a Trajectory Period Folding Method for Burnup Calculations," Energies, MDPI, vol. 15(6), pages 1-15, March.
    3. Maithah M. Alaleeli & Saeed A. Alameri & Mohammad Alrwashdeh, 2022. "Neutronic Analysis of SiC/SiC Sandwich Cladding Design in APR-1400 under Normal Operation Conditions," Energies, MDPI, vol. 15(14), pages 1-20, July.
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    Cited by:

    1. Junping Si & Guang Zhao & Yun Wang & Sheng Sun & Mingyan Tong & Wei Zhu & Jin Lei & Jinkang Cheng & Yueyan Song & Mengkang Lu, 2024. "Effect of Heat Exchange Area Margins on Thermal Characteristics of the Heat Exchange System in the Pressurized Water Test Loop during Fuel Assembly Irradiation," Energies, MDPI, vol. 17(16), pages 1-16, August.

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