Single-phase, natural circulation annular flow measurements for cartridge loop irradiation experiments

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Abstract

The nuclear industry is increasingly considering cartridge-style experiments for irradiation testing of advanced reactor fuels and materials under flowing conditions. Cartridge loops do not require the extensive support infrastructure that are necessary for external flow loops and minimize the possibility of coolant solidification over the long distance from the reactor to the external facilities. However, there is a general lack of quality flow data for internally heated fluids in an annular configuration representative of a cartridge-type irradiation experiment, particularly one with natural circulation. To address this data need, a series of experiments was conducted to measure the natural circulation flow rates of pressurized water in a sealed, internally heated vessel with annular flow conditions that represent a molten salt or sodium cartridge loop. Temperatures and flow rates were measured under steady-state and transient conditions. This paper describes the facility, methods, and results of the experiments, including the determination of nondimensional parameters. A simple 1D model of the natural convection flow rates agrees well with the experimental results. Applying this model to simulate a liquid salt cartridge experiment predicts that natural circulation flow might be able to provide liquid salt Reynolds numbers similar to those of some molten salt reactor concepts at relevant power densities.

Original languageEnglish
Article number110900
JournalNuclear Engineering and Design
Volume370
DOIs
StatePublished - Dec 15 2020

Funding

This work was conducted in conjunction with the Versatile Test Reactor project and is based upon work supported by the U.S. Department of Energy, Office of Nuclear Energy. Any opinions, findings, and conclusions or recommendations expressed in this publication are those of the authors and do not necessarily reflect the views of the U.S. Department of Energy. The authors would like to acknowledge Austin Chapel (ORNL) for leading the mechanical design of the TSTL facility modifications. Adrian Schrell (ORNL) assisted with the installation of the fiber-optic temperature sensors and provided some initial feedback on the experimental results. This work was conducted in conjunction with the Versatile Test Reactor project and is based upon work supported by the U.S. Department of Energy, Office of Nuclear Energy. Any opinions, findings, and conclusions or recommendations expressed in this publication are those of the authors and do not necessarily reflect the views of the U.S. Department of Energy. The authors would like to acknowledge Austin Chapel (ORNL) for leading the mechanical design of the TSTL facility modifications. Adrian Schrell (ORNL) assisted with the installation of the fiber-optic temperature sensors and provided some initial feedback on the experimental results.

FundersFunder number
Austin Chapel
U.S. Department of Energy
Office of Nuclear Energy
Oak Ridge National Laboratory

    Keywords

    • Cartridge
    • Flow
    • Heat transfer
    • Irradiation
    • Natural circulation
    • Natural convection

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