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Title: Calculation of natural convection test at Phenix using the NETFLOW++ code

Conference ·
OSTI ID:22107791
 [1];  [2];  [3]
  1. Research Inst. of Nuclear Engineering, Univ. of Fukui, 1-2-4, Kanawa-cho, Tsuruga, 914-0055 (Japan)
  2. Graduate School of Nuclear Power and Energy Safety Engineering, Univ. of Fukui, 1-2-4, Kanawa-cho, Tsuruga, 914-0055 (Japan)
  3. Institut National des Sciences and Techniques Nucleaires INSTN, 91191 Gif-sur-Yvette Cedex (France)

The present paper describes modeling and analyses of a natural convection of the pool-type fast breeder reactor Phenix. The natural convection test was carried out as one of the End of Life Tests of the Phenix. Objective of the present study is to assess the applicability of the NETFLOW++ code which has been verified thus far using various water facilities and validated using the plant data of the loop-type FBR 'Monju' and the loop-type experimental fast reactor 'Joyo'. The Phenix primary heat transport system is modeled based on the benchmark documents available from IAEA. The calculational model consists of only the primary heat transport system with boundary conditions on the secondary-side of IHX. The coolant temperature at the primary pump inlet, the primary coolant temperature at the IHX inlet and outlet, the secondary coolant temperatures and other parameters are calculated by the code where the heat transfer between the hot and cold pools is explicitly taken into account. A model including the secondary and tertiary systems was prepared, and the calculated results also agree well with the measured data in general. (authors)

Research Organization:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI ID:
22107791
Resource Relation:
Conference: ICAPP '12: 2012 International Congress on Advances in Nuclear Power Plants, Chicago, IL (United States), 24-28 Jun 2012; Other Information: Country of input: France; 10 refs.; Related Information: In: Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12| 2799 p.
Country of Publication:
United States
Language:
English