OUTLINE OF PWR ALTERNATE CONTROL MATERIAL INFORMATION OBTAINED AT BETTIS
Technical Report
·
OSTI ID:4323971
In evaluating Cd-In-Ag for Shippingport Pressurized Water Reactor control rods the following data resulted: tensile properties of powder metal control rod at 550 and 600F; reactivity of irradiated wrought alloy; corrosion of extruded powder metal in water at 500 to 650 deg F; and creep rupture at 550 and 600 deg F for extruded and annealed alloy. (T.R.H.)
- Research Organization:
- Westinghouse Electric Corp. Bettis Plant, Pittsburgh
- NSA Number:
- NSA-12-010629
- OSTI ID:
- 4323971
- Report Number(s):
- WAPD-PWR-PMM-1840
- Country of Publication:
- United States
- Language:
- English
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