Modelling of ROCOM Mixing Test 2.2 with TRACE v5.0 Patch 3 (NUREG/IA-0454)

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Publication Information

Manuscript Completed: April 2015
Date Published: August 2015

Prepared by:
VTT – Technical Research Centre of Finland
Nuclear Power Plant Modelling
P.O.B. 1000
02044 VTT
Finland

K. Tien, NRC Project Manager

Division of Systems Analysis
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Prepared as part of:
The Agreement on Research Participation and Technical Exchange
Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

Published by:
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

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Abstract

Experimental data on non-uniform flows in reactor pressure vessel downcomer has been recently produced at the ROCOM test facility at Helmholtz-Zentrum Dresden-Rossendorf, within the framework of the OECD/PKL2 project. This data can be used for validation of three-dimensional thermal-hydraulic codes.

The transient ROCOM test 2.2 is calculated with the system-code TRACE v 5.0 Patch 3, using the new vessel junction component in order to produce local calculation grid refinement within the lower plenum.

The simulation results obtained with TRACE are qualitatively in good agreement with the experimental measurements, but quantitatively there is more diffusion in the calculated temperature distributions and some bias from the outlet boundary condition utilized in the simulation.