RETRAN-3D results and one-dimensional analytical model for the critical power of a rod bundle with cosine-shape heating
Description
The critical power of a rod bundle with BWR parameters is assessed. Therefore we apply the RETRAN-3D code [Peterson et al., 1998] and derive an analytical model for cosine-shaped heating. The value of the model and the numerical results is assessed by comparison with an experimental investigation, which was presented by [Mitsutake et al., 1997] together with a numerical sub-channel analysis using the COBRA/BWR code. The experiment we compare with considers a single full sized BWR fuel assembly of length L that is typical of the GE-10 fuel and is referred as ''high-burnup 8 x 8 fuel''; see figure 5b in [Inoue et al., 1995]. This type of fuel consists of 60 fuel rods and one large water rod in the centre. In the experiment electrical heaters in the individual fuel rods simulate the heat production, which varies axially and horizontally. (orig.)
Additional details
Additional titles
- Original title (English)
- Jahrestagung Kerntechnik 2001. Tagungsband
Publishing Information
- Publisher
- Inforum
- Imprint Place
- Bonn (Germany)
- Imprint Title
- Annual meeting on nuclear technology 2001. Proceedings
- Imprint Pagination
- 734 p.
- Journal Page Range
- p. 333-337
- ISSN
- 0720-9207
Conference
- Title
- 2001 annual meeting on nuclear technology
- Original Conference Title
- Jahrestagung Kerntechnik (JK) 2001
- Dates
- 15-17 May 2001
- Place
- Dresden (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 32052277
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANALYTICAL SOLUTION; BWR TYPE REACTORS; FLOW RATE; FUEL ASSEMBLIES; FUEL RODS; HEATING; ONE-DIMENSIONAL CALCULATIONS; PRESSURE DEPENDENCE; R CODES; SUBCOOLING; TEMPERATURE DISTRIBUTION; THREE-DIMENSIONAL CALCULATIONS; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; COOLING; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs. Imprint:Jahrestagung Kerntechnik 2001. Tagungsband