CALCULATION-BASED DEMONSTRATION OF THE DETERMINISTIC SAFETY ANALYSIS OF A FLOATING POWER UNIT BASED ON A DESIGN-BASIS ACCIDENT SEQUENCE
- Authors
-
-
D. Baltabaev
Leading Specialists, Department of Atomic Energy and Nuclear Technologies, Agency for Atomic Energy under the Cabinet of Ministers of the Republic of Uzbekistan, Tashkent, Uzbekistan -
M. Zaripov
Leading Specialists, Department of Atomic Energy and Nuclear Technologies, Agency for Atomic Energy under the Cabinet of Ministers of the Republic of Uzbekistan, Tashkent, Uzbekistan -
Sh. Amongeldiev
Leading Specialists, Department of Atomic Energy and Nuclear Technologies, Agency for Atomic Energy under the Cabinet of Ministers of the Republic of Uzbekistan, Tashkent, Uzbekistan
-
- Keywords:
- Floating Power Unit Deterministic Safety Analysis Design-Basis Accident Decay Heat Fuel Thermal Conductivity Station Blackout Passive Safety Systems
- Abstract
- The paper presents a deterministic safety analysis of a floating power unit (FPU) using a design-basis accident sequence involving a complete station blackout and loss of core cooling following an earthquake and tsunami. An empirical decay-heat relationship and the heat-conduction equation for a fuel rod are used, with the latter solved by the Laplace integral-transform method, to estimate the time-dependent fuel centerline temperature. For the input assumptions adopted in the calculation, the fuel temperature reaches the assumed limiting value of 600 °C after approximately 1495 s (about 25 min) without cooling. This result provides an estimate of the time window available for restoring power or initiating alternative residual-heat-removal measures. The paper also discusses key safety measures for protecting floating power units against external hazards and complete loss of electrical power.
- References
-
[1] International Atomic Energy Agency, “Floating nuclear power plants,” in SMR Platform Booklet. Vienna, Austria: IAEA, 2024.
[2] International Atomic Energy Agency, Site Evaluation for Nuclear Installations, IAEA Safety Standards Series No. SSR-1. Vienna, Austria: IAEA, 2019.
[3] International Atomic Energy Agency, Safety Assessment for Facilities and Activities, IAEA Safety Standards Series No. GSR Part 4 (Rev. 1). Vienna, Austria: IAEA, 2016.
[4] International Atomic Energy Agency, The Fukushima Daiichi Accident, STI/PUB/1710. Vienna, Austria: IAEA, 2015.
[5] Decay Heat Power in Light Water Reactors, ANSI/ANS-5.1-2014 (R2023), American Nuclear Society, La Grange Park, IL, USA, 2014.
[6] International Atomic Energy Agency, Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants, IAEA Safety Standards Series No. SSG-56. Vienna, Austria: IAEA, 2020.
[7] N. E. Todreas and M. S. Kazimi, Nuclear Systems, Volume I: Thermal Hydraulic Fundamentals, 3rd ed. Boca Raton, FL, USA: CRC Press, 2021.
[8] F. P. Incropera, D. P. DeWitt, T. L. Bergman, and A. S. Lavine, Fundamentals of Heat and Mass Transfer, 7th ed. Hoboken, NJ, USA: Wiley, 2011.
[9] H. S. Carslaw and J. C. Jaeger, “The determination of Green’s function for the equation of conduction of heat in cylindrical coordinates by the Laplace transformation,” J. London Math. Soc., vol. 15, no. 4, pp. 273–281, 1940, doi: 10.1112/jlms/s1-15.4.273.
[10] International Atomic Energy Agency, Deterministic Safety Analysis for Nuclear Power Plants, IAEA Safety Standards Series No. SSG-2 (Rev. 1). Vienna, Austria: IAEA, 2019.
[11] International Atomic Energy Agency, “Fuel modelling in accident conditions (FUMAC),” IAEA, Vienna, Austria, Rep. IAEA-TECDOC-1889, 2019.
[12] International Atomic Energy Agency, Seismic Hazards in Site Evaluation for Nuclear Installations, IAEA Safety Standards Series No. SSG-9 (Rev. 1). Vienna, Austria: IAEA, 2022.
[13] International Atomic Energy Agency, Meteorological and Hydrological Hazards in Site Evaluation for Nuclear Installations, IAEA Safety Standards Series No. SSG-18. Vienna, Austria: IAEA, 2011.
[14] International Atomic Energy Agency, Safety of Nuclear Power Plants: Design, IAEA Safety Standards Series No. SSR-2/1 (Rev. 1). Vienna, Austria: IAEA, 2016.
[15] International Atomic Energy Agency, Accident Management Programmes for Nuclear Power Plants, IAEA Safety Standards Series No. SSG-54. Vienna, Austria: IAEA, 2019.