Abstract
AbstractIn this study, we conducted a neutronics analysis of a soluble-free-boron APR-1400 reactor core. Our goal was to explore the possibility of extending the fuel life cycle from 18 to 24 months. To achieve this, we examined both homogeneous and heterogeneous fuel enrichment designs while maintaining the original fuel geometries of the reactor. The proposed fuel enrichments for the homogeneous reactor core were 3.0%, 3.5%, 4.0%, 4.5%, and 4.95%. For the heterogeneous reactor core, they were (3.6%, 4.0%, 4.5%, and 5.0%) and (3.4%, 3.8%, 4.5%, and 5.0%). To suppress excess reactivity at the beginning of the fuel cycle (BOC), we applied an Integral Fuel Burnable Absorber as a thin coating layer on the outer surface of the fuel pellets. The coating was distributed uniformly throughout the core. In addition, we also studied the use of selected cladding materials as a replacement for the conventional zircaloy used in the fuel rods. The neutronics calculations for the modified APR-1400 core configuration were performed using the Serpent 2.1.31 Monte Carlo reactor physics code. We evaluated the behavior of the APR-1400 core by analyzing the effective multiplication factor, flux spectrum, pin power distribution, and radial power profile. Both the homogeneous and heterogeneous cores were compared with the reference APR-1400 core configuration. Our results indicate that it is possible to extend the fuel cycle to up to 24 months in both the homogeneous and heterogeneous cores. We also conducted a thorough analysis of the initial cycle for heterogeneous cores to consider more realistic scenarios.
Funder
UAE Ministry of Education
Publisher
Springer Science and Business Media LLC
Reference30 articles.
1. International Atomic Energy Agency. "Nuclear power in figures." Retrieved from https://www.iaea.org/topics/nuclear-power-in-figures (2020).
2. Garcia-Delgado, L.; Driscoll, M.J.; Meyer, J.E.; Todreas, N.E.: An economically optimum PWR reload core for a 36-month cycle. Ann. Nuclear Energy 26(8), 659–677 (1999)
3. Rosenstein, R. G.; Sipes, D. E.; Beall, R. H.; Donovan, E. J.: 24-month fuel cycles. In: Proceedings of the Topical Meeting on Advances in Fuel Management (1986).
4. Fernández-Arias, P.; Vergara, D.; Orosa, J.A.: A global review of PWR nuclear power plants. Appl. Sci. 10(13), 4434 (2020)
5. Schlieck, M.; Berger, H.D.; Neufert, A.: Optimized gadolinia concepts for advanced in-core fuel management in PWRs. Nucl. Eng. Des. 205(1–2), 191–198 (2001)
Cited by
2 articles.
订阅此论文施引文献
订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献