Supporting Analysis for Thermal Suitability of Fuel Elements for SM-1A Core I Loading
Description:
A recommended SM-1A Core I loading chart was derived from available, metallurgically acceptable elements at the SM-1A and SM-1 sites. The derivation was based on local thermal and hydraulic considerations of minimum elementto- element coolant channel clearances. These clearances were determined from field inspection measurements of outer fuel plate spacing, as modified by analytical calculations of plate ripple growth during exposure to reactor operating thermal stresses. (auth)
Date:
January 10, 1962
Creator:
Brondel, J. O.
Item Type:
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Partner:
UNT Libraries Government Documents Department