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
Additional details
Publishing Information
- Imprint Pagination
- 82 p.
- Report number
- NUREG/CR--1124
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11522156
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CODES; F CODES; FISSION PRODUCTS; FUEL RODS; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; RADIOACTIVITY TRANSPORT; REACTOR CORE DISRUPTION; REACTOR SAFETY; SWELLING; URANIUM DIOXIDE
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; BREEDER REACTORS; CHALCOGENIDES; DEFORMATION; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; ISOTOPES; LIQUID METAL COOLED REACTORS; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Secondary number(s)
- SAND--78-1790.