ML19345G486
| ML19345G486 | |
| Person / Time | |
|---|---|
| Issue date: | 09/29/1980 |
| From: | Zeile H NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Tiller R ENERGY, DEPT. OF, IDAHO OPERATIONS OFFICE |
| Shared Package | |
| ML19345G484 | List: |
| References | |
| HJZ-317-80, NUDOCS 8104070364 | |
| Download: ML19345G486 (1) | |
Text
.
.u e,..,,
OG App e ndix B E.
September 29, 1980 9
Mr. R. E. Tiller, Director Reactor Operations and Program Division Idaho Operations Office - DOE Idaho Falls. ID 83401 STEADY STATE FUEL RUBBLE THERMAL ANALYSIS - HJZ-317-80
Dear Mr. Tiller:
The attached summary documents the results of a steady state thermal analysis of a ballooned PWR fuel rod during a LOCA accident as requested
~
by Dr. M. L. Picklesimer (NRC). The objective of this analysis was to calculate fuel rod temperature distributions in the region where the cladding has ballooned. Fuel redistribution within the ballooned region was considered and a stagnate steam environment and decay heat at 100 s was assumed.
[
Based on the analysis, the calculated cladding temperature for the worst case (about 90% cladding strain and 160% fuel redistribution) was about 230 K greater than the nominal case of no ballooning or fuel redistribu-tion. Additionally, the maximum fuel temperature within the ballooned region was 1300 K higher than the nominal case. Both temperatures are well below the melting point of the respective materials, indicating that fuel redistribution into a balloon for these conditions will not pose a significant problem during a LOCA accident.
l This analysis was intended to provide a "first-cut" evaluation of fuel rod temperatures for a number of assumed conditions.
If deemed necessary, a more refined evaluation could be completed that would include a simple computer model and improved estimates of the fuel and gap properties, and fuel distribution within the rod.
Very truly yours, Y. O fhV H. J. Zeile, Manager l
Thermal Fuels Behavior Program TRY/bh
Attachment:
As stated
,(*
8104 070 Mh
._