Published 2009 | Version v1
Miscellaneous

Experimental study on void behavior in fast power transients simulating hot stand-by reactivity initiated accidents of BWR

  • 1. Japan Atomic Energy Agency, Nuclear Safety Research Center, Tokai, Ibaraki (Japan)

Description

A series of experiments was performed in order to acquire insights on transient void behavior at high pressures, which simulated thermal-hydraulic conditions during a reactivity initiated accidents (RIA) at a hot stand-by condition of boiling water reactors (BWRs). A simulated fuel rod placed in the test section was rapidly heated by the direct electric current. The void fraction in the flow channel was evaluated from the measured impedance of a water-vapor mixture with use of the rod and the outer boundary wall as a pair of electrodes. The experimental results implied that key influential factors were the subcooling of the inlet water and the ambient pressure. Heat partitioning was estimated through energy balance calculations, which showed that heat consumed for the water heat-up was sharply decreased within a narrow range of water temperature adjacent to the saturation. The experimental results were applied to the analyses with TRAC-BF1 and RELAP5-Mod3 codes to assess the predictive capability of the best-estimate (BE) thermal-hydraulic codes. (author)

Part of:
NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics

Additional details

Publishing Information

Imprint Title
NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics
Imprint Pagination
[4617 p.]
Journal Page Range
[15 p.]

Conference

Title
13. international topical meeting on nuclear reactor thermal hydraulics
Acronym
NURETH-13
Dates
27 Sep - 2 Oct 2009
Place
Kanazawa, Ishikawa (Japan)

Optional Information

Notes
Available as CD-ROM Data in PDF format, Folder Name: FullPaper, Paper ID: N13P1181.pdf