Published 1989
| Version v1
Book
Advanced subchannel analysis for BWR fuel bundle
Creators
Description
A reload bundle with a large critical power margin introduces flexibility into reload fuel management. An important design objective is therefore optimization of the bundle and spacer geometry in order to maximize the bundle critical power. With a view to reducing the extent of the complex full-scale tests usually carried out to determine the thermal hydraulic characteristics of various bundle geometries, the subchannel analysis method was further developed with the KWU computer code RINGS. The code, qualified with test data from various 9x9 bundles, accounts for subchannel flow using an annular flow model with a liquid film on the heated rods and determines dryout by calculating the film thickness. (orig.)
Additional details
Publishing Information
- Publisher
- Braun.
- Imprint Place
- Karlsruhe (Germany, F.R.)
- ISBN
- 3-7650-1115-0
- Imprint Title
- Fourth international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4). Proceedings. Vol. 1
- Imprint Pagination
- 745 p.
- Journal Page Range
- p. 555-559.
Conference
- Title
- 4. international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4).
- Dates
- 10-13 Oct 1989.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 22029360
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; CONFIGURATION; DRYOUT; FILM BOILING; FUEL ELEMENT CLUSTERS; FUEL MANAGEMENT; HYDRAULICS; POWER DENSITY; VERIFICATION
- Descriptors DEC
- BOILING; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS