Published November 1979 | Version v1
Report Restricted

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

Description

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

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A05/MF A01.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
82 p.
Report number
NUREG/CR--1124

Optional Information

Secondary number(s)
SAND--78-1790.