Published 2007
| Version v1
Report
Contributions to and expectations from the CRP - Argonne National Laboratory (USA)
Creators
- 1. Nuclear Engineering Division, Argonne National Laboratory, Argonne, IL (United States)
Description
For us, the chief benefit of the CRP will be validation of multidimensional fluid dynamics capabilities for analysis of outlet plenum temperature distributions. As reactor designers seek new fuel handling features to reduce costs, upper internal structure configurations are becoming more compact, and higher fidelity analysis techniques are required to assess thermal stresses. Argonne currently has 1) a reactor systems analysis code with an experimentally-based model for plenum stratification, 2) the COMMIX code (parent of the JAEA AQUA code), and 3) commercial fluid dynamics analysis codes. It is anticipated that all or some combination of these capabilities will be employed to perform the CRP analysis
Additional details
Publishing Information
- Imprint Title
- Consultants' meeting (preparatory meeting) on the IAEA Coordinated Research Project (CRP) on 'Benchmark analyses of sodium natural convection in the upper plenum of the MONJU reactor vessel'. Working material
- Imprint Pagination
- 12 p.
- Journal Page Range
- p. 8
- Report number
- TWG-FR--133
Conference
- Title
- Consultants' meeting (preparatory meeting) on the IAEA Coordinated Research Project (CRP) on 'Benchmark analyses of sodium natural convection in the upper plenum of the MONJU reactor vessel'
- Dates
- 11 May 2007
- Place
- Tsuruga (Japan)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44057258
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANL; CONFIGURATION; COST; FLUID MECHANICS; FUEL MANAGEMENT; JAEA; SYSTEMS ANALYSIS; TEMPERATURE DISTRIBUTION; THERMAL STRESSES; VALIDATION
- Descriptors DEC
- JAPANESE ORGANIZATIONS; MANAGEMENT; MECHANICS; NATIONAL ORGANIZATIONS; NUCLEAR MATERIALS MANAGEMENT; STRESSES; TESTING; US AEC; US DOE; US ERDA; US ORGANIZATIONS
Optional Information
- Notes
- This record replaces 39009321