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Neutronic analysis of nanofluids as a coolant in the Bushehr VVER - 1000 reactor

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Języki publikacji
EN
Abstrakty
EN
The main goal of this study was to perform the neutronic analysis of nanofluids as a coolant in reactor simulation. The variation of multiplication factor and thermal power have been investigated in the Bushehr VVER-1000 reactor core with using different nanofluids as coolant. In the applied analysis, water-based nanofluids containing various volume fractions of Al2O3, TiO2, CuO and Cu nanoparticles were used. The addition of different types and volume fractions of nanoparticles were found to have various effects on reactor neutronic characteristics. By using WIMS-D5 and CITATION code, the appropriate nanofluid with optimum volume percentage of nanoparticles was achieved. The results show that at low concentration (0.1% volume fraction) alumina is the optimum nanoparticle for normal reactor operation.
Słowa kluczowe
Czasopismo
Rocznik
Strony
375--381
Opis fizyczny
Bibliogr. 10 poz., rys.
Twórcy
autor
autor
  • Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran, Tel./Fax: +98 21 44817170 4, rezajahan@yahoo.com
Bibliografia
  • 1. AEOI (2010) Album of Reactor Core Neutronic Characteristics of the Initial Fuel Inventory. Technical Report, 51.BU.1 0.00.AB.WI.ATEX.011. Atomic Energy Organization of Iran, Tehran
  • 2. Buongiorno J, Hu LW, Apostolakis G, Hanninka R, Lucasa T, Chupin A (2009) A feasibility assessment of the use of nanofluids to enhance the in-vessel retention capability in light-water reactors. Nucl Eng Des 239;5:941–948
  • 3. Buongiorno J, Truong B (2005) Preliminary study of water-based nanofluid coolants for PWRs. Trans Am Nucl Soc 92:383–384
  • 4. BUSHEHR VVER-1000 reactor (2003) Final Safety Analysis Report of Bushehr Nuclear Power Plant (FSAR of BNPP-1). Chapter 4. Ministry of Russian Federation of Atomic Energy (Atomenergoproekt), Moscow
  • 5. Fowler TB (1999) CITATION-LDI2 Nuclear Reactor Core Analysis Code System. CCC-643. Oak Ridge National Laboratory, Oak Ridge, Tennessee
  • 6. Hadad K, Hajizadeh A, Jafarpour K, Ganapo BD (2010) Neutronic study of nanofluids application to VVER-1000. Ann Nucl Energy 37:1447–1455
  • 7. Malmir H, Maleki N, Zahedinejad E (2010) Comparison between triangular and hexagonal modeling of a hexagonal-structured reactor core using box method. Ann Nucl Energy 38;2/3:371–378
  • 8. Rahmani Y, Zarifi E, Pazirandeh A (2010) Study of boron dilution phenomenon in the core and fuel assemblies of Bushehr VVER-1000 reactor in normal operating condition. Nukleonika 55;3:323–330
  • 9. Velagapudi V, Konijeti RK, Aduru CS (2008) Empirical correlation to predict thermophysical and heat transfer characteristics of nanofluids. Thermal Science 12;2:27–37
  • 10.WIMS D-5B (98/11) Deterministic Multigroup Reactor Lattice Calculations. NEA-1507 (1999) Atomic Energy Establishment, Winfrith, Dorchester
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-article-BUJ8-0023-0021
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