ML19221A416
| ML19221A416 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 04/14/1979 |
| From: | NRC COMMISSION (OCM) |
| To: | |
| References | |
| OLS-790414, NUDOCS 7905220464 | |
| Download: ML19221A416 (3) | |
Text
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1 TMI-2 Fuel Dam s'
Examinations of data frto core thermocouples, inco,re and excore ion cha-ters.
and analyses of core parannters such as primry coolant pressure for the first dozen hours of the transient shows three periods of significant core uncovery.
That is, 3 time periods during which portions of the fuel assemblies were cooled by steam rather than pressurized water which is the norml cooling nie thod.
It was
/during these periods of deficient cooling that extensive damage to the fuel
~
occurred. This damage occurred prirnarily by exidation of the fuel as-sechlies, zirconium alloy cceponents, which were embrittled and lost struc-tural integrity in the affected regions of the core.
Estimates of the and extent of damge were calculated from fission product / hydrogen releases inside the plant and radiochemical analysis of the reactor coolant water.
The region of extensive structural dacuge is probably confined to the upper 40% of the core. These analyses indicated that some of the fuel may have reached temperatures as high as 3500 *F and that rupturing of virtually all the fuel rods occurred.
The melting point of uranium dioxide fuel is 5100
'F, thus it is unlikely that fuel relting occurred.
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