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A study of the effects of changing burn-up and gap gaseous compound on the gap convection coefficient (in a hot fuel pin) in VVER-1000 reactor

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Języki publikacji
EN
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EN
In this article we worked on the result and process of calculation of the gap heat transfer coefficient for a hot fuel pin in accordance with burn-up changes in the VVER-1000 reactor at the Bushehr nuclear power plant (Iran). With regard to the fact that in calculating the fuel gap heat transfer coefficient, various parameters are effective and the need for designing a model is being felt, therefore, in this article we used Ross and Stoute gap model to study impacts of different effective parameters such as thermal expansion and gaseous fission products on the hgap change rate. Over time and with changes in fuel burn-up some gaseous fission products such as xenon, argon and krypton gases are released to the gas mixture in the gap, which originally contained helium. In this study, the composition of gaseous elements in the gap volume during different times of reactor operation was found using ORIGEN code [3]. Considering that the thermal conduction of these gases is lower than that of helium, and by using the Ross and Stoute gap model, we find first that the changes in gaseous compounds in the gap reduce the values of gap thermal conductivity coefficient, but considering thermal expansion (due to burn-up alterations) of fuel and clad resulting in the reduction of gap thickness we find that the gap heat transfer coefficient will augment in a broad range of burn-up changes. These changes result in a higher rate of gap thickness reduction than the low rate of decrease of heat conduction coefficient of the gas in the gap during burn-up. Once these changes have been defined, we can proceed with the analysis of the results of calculations based on the Ross and Stoute model and compare the results obtained with the experimental results for a hot fuel pin as presented in the final safety analysis report of the VVER-1000 reactor at Bushehr [2]. It is noteworthy that the results of accomplished calculations based on the Ross and Stoute model correspond well with the existing experimental results for this reactor.
Czasopismo
Rocznik
Strony
93--95
Opis fizyczny
Bibligr. 4 poz., rys.
Twórcy
autor
autor
  • Department of Nuclear Engineering, Faculty of Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran, Tel.: 009821 44817166, Fax: 009821 44817194, yashar.rahmani@gmail.com
Bibliografia
  • 1. Ainscough JB (1982) Gap conduction in Zircaloy-Clad LWR fuel rods. Committee of the Safety of Nuclear Installations OECD Nuclear Energy Agency, Paris, France
  • 2. Final Safety Report for BUSHEHR VVER-1000 Reactor,Chapter 4 (2003) Ministry of Russian Federation of Atomic Energy (Atomenergoproekt), Moscow
  • 3. ORNL (1973) ORIGEN Code Manual. ORNL-4628,Oak Ridge National Laboratory, Oak Ridge, Tennessee
  • 4. Todress N, Kazimi MS (1982) Nuclear system I.Hemisphere Publishing Corporation, New York
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-article-BUJ6-0023-0050
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