Computational Fluid Dynamic Analysis for the Proposed VHTR Lower Plenum Standard Problem

Technical Report · Mon Sep 01 04:00:00 EDT 2008

DOI:https://doi.org/10.2172/1389179· OSTI ID:1389179

Johnson, R. W. ^[1]; Pointer, W. David ^[1]; Schultz, Richard R. ^[1]

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1. Idaho National Lab. (INL), Idaho Falls, ID (United States)

One of the reference designs for the Next Generation Nuclear Plant (NGNP) is a prismatic reactor configuration. A major concern in the operation of this design is the nature of the flow of hot gas as it exits the core into the lower plenum and then out the vessel exit duct. The two primary areas of concern are the impingement of hot jets onto the walls of the lower plenum and the degree of thermal mixing of the helium coolant as it flows out of the reactor vessel. Computational fluid dynamic (CFD) simulations have been proposed by general consensus to estimate the desired local fluid dynamic and temperature information. Successful CFD simulations require careful planning and extensive calculations to help ensure that they accurately represent the flow physics. An important aspect of the application of CFD is to validate the results against detailed validation data, for scaled problems that involve similar physics. A section of the lower plenum of the reference prismatic NGNP was employed to create a scaled model to use to obtain experimental data for use as validation data to compare with a CFD analysis. Extensive flow data were obtained from the scaled model while installed in the INL’s Matched Index of Refraction (MIR) test facility.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1389179
• Report Number(s): INL/EXT--08-14746
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CFD
Lower Plenum
NGNP
Standard Problem
VHTR