In-vessel thermal-hydraulic analysis
In-vessel thermal-hydraulic analysis
This paper presents some recent results obtained from the COMMIX-1A code for the EBR-II reactor transient No. 10, Phase 2. Both the reactor vessel and the neutron shield assembly and assembly arrangement in the reactor core are shown. The computational grid system used in COMMIX-1A is presented. Reactor flow and power transients are shown. Velocity and temperature distributions at steady state and t (time) = 60 sec are included. Finally, a comparison between the calculated results from COMMIX-1A and experimental measurements are presented for outlet temperatures for driver subassembly of XX08, top-of-core temperature for driver subassembly of XX08, and low-pressure plenum mass flow respectively.
- University of North Texas United States
- University of North Texas United States
- Karlsruhe Institute of Technology Germany
ddc:620, Ebr-2 Reactor, Temperature Gradients, Reactor Cores, Hydraulics, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Breeding, Mechanics, Sodium Cooled Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety, Transients, Fbr Type Reactors, Research And Test Reactors, Lmfbr Type Reactors, 220600 -- Nuclear Reactor Technology-- Research, Reactor Components, Engineering & allied operations, Computer Calculations, 22 General Studies Of Nuclear Reactors, Reactor Safety, Breeder Reactors, Test & Experimental Reactors, Heat Transfer, Reactors, 210500 -- Power Reactors, 620, Power Reactors, Energy Transfer, Fast Reactors, Epithermal Reactors, Temperature Distribution, Safety, Experimental Reactors, info:eu-repo/classification/ddc/620, Liquid Metal Cooled Reactors
ddc:620, Ebr-2 Reactor, Temperature Gradients, Reactor Cores, Hydraulics, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Breeding, Mechanics, Sodium Cooled Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety, Transients, Fbr Type Reactors, Research And Test Reactors, Lmfbr Type Reactors, 220600 -- Nuclear Reactor Technology-- Research, Reactor Components, Engineering & allied operations, Computer Calculations, 22 General Studies Of Nuclear Reactors, Reactor Safety, Breeder Reactors, Test & Experimental Reactors, Heat Transfer, Reactors, 210500 -- Power Reactors, 620, Power Reactors, Energy Transfer, Fast Reactors, Epithermal Reactors, Temperature Distribution, Safety, Experimental Reactors, info:eu-repo/classification/ddc/620, Liquid Metal Cooled Reactors
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