Thermal-hydraulic aspects of flow inversion in a research reactor

Conference · Sat Nov 01 00:00:00 EST 1986

OSTI ID:6819218

Smith, R S; Woodruff, W L

PARET, a neutronics and thermal-hydraulics computer code, has been modified to account for natural convection in a reactor core. The code was then used to analyze the flow inversion that occurs in a reactor with heat removal by forced convection in the downward direction after a pump failure. Typical results are shown for a number of parameters. Research reactors normally operating much above ten MW are predicted to experience nucleate boiling in the event of a flow inversion. Comparison with experimental results from the Belgian BR2 reactor indicated general agreement although nucleate boiling that was analytically predicted was not noted in the BR2 data.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6819218
• Report Number(s): CONF-861185-7; ON: DE87004751; TRN: 87-008016
• Resource Relation: Conference: Reduced Enrichment for Research and Test Reactors (RERTR) program international meeting, Gatlinburg, TN, USA, 3 Nov 1986
• Country of Publication: United States
• Language: English

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