FISGAS: a code for fission-gas migration and fuel swelling in an LMFBR accident

Technical Report · Thu Nov 01 04:00:00 EST 1979

OSTI ID:5899245

Ostensen, R W

A new computer program, FISGAS, has been written to model the microscopic behavior of fission-gas in uranium dioxide reactor fuel and its effect on the macroscopic swelling of that fuel in a reactor accident. A radial multinode capability is provided. Separate calculations are provided for gas bubble motion and coalescence and gas transfer inside the grain, on the grain face, and on the grain edge. Microscopic modeling of the gas bubbles includes vacancy-flow restriction on the bubble size and macroscopic pressure field restraint on bubble growth. The pressure field is controlled by the fuel swelling rate which is limited by macroscopic creep. FISGAS is primarily designed to provide a diagnostic tool for the Fuel Disruption test series being performed in the Annular Core Research Reactor at Sandia Laboratories.

• Research Organization: Sandia Labs., Albuquerque, NM (USA)
• DOE Contract Number: EY-76-C-04-0789
• OSTI ID: 5899245
• Report Number(s): NUREG/CR-1124; SAND-78-1790
• Country of Publication: United States
• Language: English

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