Analysis of the atomic ratio of H and Zr effect on the neutronics parameters of ZrH moderated space nuclear reactor
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Zirconium hydride (ZrH) is an ideal moderator for space nuclear reactors due to its exceptional properties, including high hydrogen content, small neutron absorption cross section, and high operating temperature. The primary goal of this study is to examine how the atomic ratio of H to Zr (H/Zr ratio) influences the neutronics parameters of a ZrH moderated space nuclear reactor, with a focus on establishing a reliable reference for ensuring the optimal safety and minimization of such reactors. The neutronics calculation based on the ZrH moderated space nuclear reactor named Topaz-II is performed using the Reactor Monte Carlo code (RMC code) with the ENDF/VII cross-section database. The effects of the H/Zr ratio were studied with a particular focus on the initial keff, the burnup, the temperature reactivity coefficient and the criticality safety. The results show that with the increase of the H/Zr ratio, the initial keff increases while the drums’ worth decreases. The Moderator Temperature Coefficient (MTC) is a positive value that rises as the H/Zr ratio increases. In the dropping accidents, the reactor full of voids with seawater is more serious, and the introduced reactivity decreases with the increase of the H/Zr ratio.
Abstract
Zirconium hydride (ZrH) is an ideal moderator for space nuclear reactors due to its exceptional properties, including high hydrogen content, small neutron absorption cross section, and high operating temperature. The primary goal of this study is to examine how the atomic ratio of H to Zr (H/Zr ratio) influences the neutronics parameters of a ZrH moderated space nuclear reactor, with a focus on establishing a reliable reference for ensuring the optimal safety and minimization of such reactors. The neutronics calculation based on the ZrH moderated space nuclear reactor named Topaz-II is performed using the Reactor Monte Carlo code (RMC code) with the ENDF/VII cross-section database. The effects of the H/Zr ratio were studied with a particular focus on the initial keff, the burnup, the temperature reactivity coefficient and the criticality safety. The results show that with the increase of the H/Zr ratio, the initial keff increases while the drums’ worth decreases. The Moderator Temperature Coefficient (MTC) is a positive value that rises as the H/Zr ratio increases. In the dropping accidents, the reactor full of voids with seawater is more serious, and the introduced reactivity decreases with the increase of the H/Zr ratio.
참고문헌 (21)
- NASA Technology Roadmaps-TA3, Space power and energy storage, "NASA", NASA, ~ (2015)
- "The Role of Nuclear Power and Nuclear Propulsion in the Peaceful Exploration of Space" (2005)[URL]
- Kelsa, "Moderator considerations for space nuclear power and propulsion systems", Nuclear and Emerging Technologies for Space 2021 (2021)
- Z. H. Wang, "Advance in and prospect of moderator materials for space nuclear reactors", Int. J. Energy Res, (2021), pp.1~17 (2021)[DOI]
- "SNAP (space nuclear auxiliary power), Reactor Overview" (1984)[URL]
- Cockeram, "SNAP 2, 8, and 10A Reactor Programs Progress Report", Progress in Astronautics and Rocketry, 16, pp.393~415 (1966)[DOI]
- "TOPAZ II system description" (1994)[URL]
- E. Proust, "Space Nuclear Power Studies in FranceOverview of the Erato Program", ~ (1988)
- Z. W. Dai, "Numerical simulation on thermal-hydraulic and thermoelectric characteristics of the TOPAZ-II reactor core", Int. J. Energy Res, 45, pp.12159~12172 (2021)[DOI]
- Z. W. Dai, "Thermoelectric characteristics analysis of thermionic space nuclear power reactor", Int. J. Energy Res, 0 (2019)[DOI]
- Z. Y. Wu, "Transient thermal–hydraulic analysis of the thermionic space reactor TOPAZ-II", Ann. Nucl. Energy, 194, pp.110054~ (2023)[DOI]
- J. C. Xie, "Analysis of temperature effect of modifier of TOPAZ-IIReactor", Atom, Energy Sci. Technol, 1, pp.48~51 (2011)[DOI]
- Intermediate Heterogeneous Assembly with Highly Enriched Uranium Dioxide (96% 235U) and Zirconium Hydride Moderator, "Y. S. Glushkov", OECD, NSC, pp.1995, ~[DOI]
- Intermediate Heterogeneous Assembly with Highly Enriched Uranium Dioxide and Sand, "Water Radial Reflector", E. S. Glouchkov, NEA, pp.NSC, 1996[DOI]
- M. T. Simnad, "The U-ZrHx alloy : its properties and use in TRIGA fuel", Nucl. Eng. Des, 64(3), pp.403~422 (1981)[DOI]
- Properties of uranium-zirconium hydride moderated nuclear fuel synthesized by powder metallurgy, "C. Taylor", Los Alamos National Laboratory, ~, pp.LA-UR-22-29969 (2022)
- K. Wang, "RMC–A Monte Carlo code for reactor core analysis", Ann. Nucl. Energy, 82, pp.121~129 (2015)[DOI]
- M. B. Chadwick, "ENDF", B-VII. 0 : next generation evaluated nuclear data library for nuclear science and technology, 2006, pp.107, 2931~3060
- S. C. Liu, "Development of on-the-fly temperature-dependent cross-sections treatment in RMC code", Ann. Nucl. Energy, 94, pp.144~149 (2016)[DOI]
- L. P. Wang, "Application of SiO2 thermal neutron scattering cross sections in space reactor accident analysis", Atom. Energy Sci. Technol, 48(4), pp.680~684 (2014)[DOI]
- Compendium of Material Composition Data for Radiation Transport Modeling, "R.G. Williams", office of scientific & technical information, ~ (2011)
