Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core
Mohammad Alrwashdeh () and
Saeed A. Alameri ()
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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
Energies, 2022, vol. 15, issue 21, 1-16
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.
Keywords: nuclear fuel; PWR; accident-tolerant fuel; chromium coating (search for similar items in EconPapers)
JEL-codes: Q Q0 Q4 Q40 Q41 Q42 Q43 Q47 Q48 Q49 (search for similar items in EconPapers)
Date: 2022
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Citations: View citations in EconPapers (1)
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