Calculation of natural convection test at Phenix using the NETFLOW++ code
Creators
- 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)
Description
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)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-091-1
- Imprint Title
- Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12
- Imprint Pagination
- 2799 p.
- Journal Page Range
- p. 1771-1780
Conference
- Title
- 2012 International Congress on Advances in Nuclear Power Plants
- Acronym
- ICAPP '12
- Dates
- 24-28 Jun 2012
- Place
- Chicago, IL (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 44065602
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOUNDARY CONDITIONS; COMPUTER CALCULATIONS; COMPUTER CODES; COOLANTS; JOYO REACTOR; NATURAL CONVECTION; NUCLEAR POWER PLANTS; PHENIX REACTOR; PRIMARY COOLANT CIRCUITS; SIMULATION; WATER
- Descriptors DEC
- BREEDER REACTORS; CONVECTION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT TRANSFER; HYDROGEN COMPOUNDS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MASS TRANSFER; NUCLEAR FACILITIES; OXYGEN COMPOUNDS; PLUTONIUM REACTORS; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; THERMAL POWER PLANTS
Optional Information
- Notes
- 10 refs.