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

Part of:
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

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