Abstract
Prospects for enhancing heat transfer in the core of reactor plants by using annular fuel elements are considered. Advantages of changing over to use of annular fuel elements are analyzed, and problems that must be solved are identified. It is shown that application of annular fuel elements makes it possible to increase the specific power of a reactor while keeping its safety indicators at a high level.
Similar content being viewed by others
References
P. L. Kirillov and G. P. Bogoslovskaya, Heat Exchange in Nuclear Power Installationss (Energoatomizdat, Moscow, 2000) [in Russian].
Greenspan et al., “Optimization of UO2 Fueled PWR Core Design,” in Proceedings of Workshop on Advanced Reactors with Innovative Fuels (ARWIF—2005), February 16–18, 2005, Oak Ridge, TN, the United States.
J. Zhao, H. C. No, and M. S. Kazimi, “Mechanical Analysis of High Power Internally Cooled Annular Fuel,” Nucl. Technol. 146 (2004).
D. Feng, P. Hejzlar, and M. S. Kazimi, “Thermal Hydraulic Design of High Power Density Fuel for PWRs,” in Proceedings of NURETH-10, Seoul, Korea, 2003.
P. Hejzlar, M. J. Driscoll, and M. S. Kazimi, “High Performance Annular Fuel for Pressurized Water Reactors,” Trans. Amer. Nucl. Soc. 84, 192 (2001).
K. L. Lee and S. H. Chang, “A Study of the Conceptual Design of a 1,500 MWe Passive PWR with Annular Fuel,” in Proceedings of ICAPP’04, Pittsburg, PA, the United States, June 13–17, 2004, paper 4170.
C. M. Mildrum, “Economic Evaluation of Annular Fuel for PWRs,” Trans. Amer. Nucl. Soc. 35, 78 (1980).
M. Caner and E. T. Dugan, “ThO-UO Annular Fuel Pins for High Burnup Fuels,” Ann. Nucl. Energy 27, 759 (2000).
R. G. Buas, “Annular Fuel Element for High Temperature Reactors,” U.S. Patent 3(928), 132 (1975).
E. A. Boltenko, “Burnout in Annular Channels with Flow Swirling,” Teploenergetika, No. 11, 25–30 (2003) [Therm. Eng., No. 11 (2003)].
V. N. Blinkov and E. A. Boltenko, “A Fuel Assembly,” RF Patent No. 2220464 MCI 3G 21C3/00, 3/30, 3/32, Izobret. No. 36 (2003).
V. D. Terent’ev, Principles of Thermal and Hydraulic Calculations of Marine Propulsion Nuclear Reactors and Steam Generators (Sudostroenie, Leningrad, 1967) [in Russian].
V. N. Blinkov, E. A. Boltenko, I. V. Elkin, et al., “The Concept of a Nuclear Power Installation with a Reactor Core Constructed Using Tubular Fuel Elements,” in Proceedings of the Scientific-Technical Conference-2008 “New-Generation Nuclear Fuel for Nuclear Power Stations. Results of Development, Operating Experience, and Lines for Future Development,” Moscow, November 19–21, 2008 (VNIINM, Moscow, 2008).
B. A. Dement’ev, Nuclear Power Reactors (Energoatomizdat, Moscow, 1990) [in Russian].
P. Hejzlar and M. S. Kazimi, High Performance Fuel Design for Next Generation PWR: Final Report, Project DE-FG-03-01SF22329.2006 (MIT Center for Advanced Nuclear Energy Systems, MA, the United States).
Author information
Authors and Affiliations
Additional information
Original Russian Text © V.N. Blinkov, E.A. Boltenko, I.V. Elkin, O.I. Melikhov, S.L. Solov’ev, 2010, published in Teploenergetika.
Rights and permissions
About this article
Cite this article
Blinkov, V.N., Boltenko, E.A., Elkin, I.V. et al. Prospects for using annular fuel elements in nuclear power engineering. Therm. Eng. 57, 213–218 (2010). https://doi.org/10.1134/S0040601510030043
Published:
Issue Date:
DOI: https://doi.org/10.1134/S0040601510030043