Development of Coupled SCALE4.2/GTRAN2 Computational Capability for Advanced MOX Fueled Assembly Designs

Conference · Sun Apr 30 00:00:00 EDT 1995

OSTI ID:64142

Vujic, Jasmina ^[1]; Greenspan, Ehud ^[1]; Slater, Steve ^[1]; Postma, Todd ^[1]; Leal, Luiz ^[2]; Casher, Greg ^[1]; Soares, Ilson ^[1]

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1. Univ. of California, Berkeley, CA (United States)
2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

An advanced assembly code system that can efficiently and accurately analyze various designs (current and advanced) proposed for plutonium disposition is being developed by "marrying" two existing state-of-the-art methodologies-GTRAN2 and SCALE 4.2. The resulting code system, GT-SCALE, possess several unique characteristics: exact 2D representation of a complete fuel assembly, while preserving the heterogeneity of each of its pin cells; flexibility in the energy group structure, the present upper limit being 218 groups; a comprehensive cross-section library and material data base; and accurate burnup calculations. The resulting GT-SCALE is expected to be very useful for a wide variety of applications, including the analysis of very heterogeneous UO₂ fueled LWR fuel assemblies; of hexagonal shaped fuel assemblies as of the Russian LWRs; of fuel assemblies for HTGRs; as well as for the analysis of criticality safety and for calculation of the source term of spent fuel.

• Research Organization: Univ. of California, Berkeley, CA (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 64142
• Report Number(s): CONF-950420-23; ON: DE95010522; TRN: 95:014089
• Resource Relation: Conference: 16. International Conference on Mathematics and Computations, Reactor Physics, and Environmental Analyses, ANS Topical Meeting, Portland, OR (United States), 30 Apr - 4 May 1995; Other Information: PBD: [1995]
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
97 MATHEMATICS AND COMPUTING
FUEL ASSEMBLIES
DESIGN
WATER COOLED REACTORS
G CODES
BENCHMARKS
MIXED OXIDE FUELS
Nuclear Criticality Safety Program (NCSP)
Light Water Reactor (LWR) Fuel Assemblies
Mixed Oxide (MOX) Fuel
Fuel Pellets
Plutonium Burner Core Calls
Modular High-Temperature Gas-Cooled Reactors (MHTGRs)
Boiling Water Reactor (BWR)
Pin Cell Geometry