Published October 10, 1997 | Version v1
Miscellaneous

TEMPUL, Temperature Distribution in Fuel Element after Pulse

  • 1. 'Jozef Stefan' Institute, Reactor physics division, Jamova 39, PO. BOX 3000, 1001 Ljubljana (Slovenia)
  • 2. Agencija za radioaktivne odpadke, Parmova ulica 53, 1000 Ljubljana (Slovenia)

Description

1 - Description of program or function: A computer program for temperature distribution calculations in fuel element after the pulse. 2 - Method of solution: The program solves the diffusion equation for heat transfer in one-dimensional cylindrical geometry using simple finite-difference method. 3 - Restrictions on the complexity of the problem: The program is provided with the necessary database consisting of material properties for : 1-zirconium, 2-stainless steel, 3-fuel with 12 w/o uranium and 20% enrichment, 4-fuel with 8.5 w/o uranium and 20% enrichment, 5-FLIP fuel with 8.5 w/o uranium and 70% enrichment, 6-LEU fuel with 20 w/o uranium and 20% enrichment and 7-water. The gap can either be filled with air or with Helium. The gap also can be omitted. The number of output-times for the radial temperature distribution is limited to 11.

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Notes
10 refs.