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PRELIMINARY DESIGN REPORT-PROTOTYPE STEAM GENERATOR. VOL. 2. STRESS ANALYSIS. SODIUM-HEATED STEAM GENERATOR DEVELOPMENT
None
Date:
November 15, 1965
Creator:
Hocking, J.E.
System:
The UNT Digital Library
PRELIMINARY DESIGN REPORT-PROTOTYPE STEAM GENERATOR. VOL. 3. EFFECTS OF SODIUM-WATER REACTION ON STEAM GENERATOR. SODIUM-HEATED STEAM GENERATOR DEVELOPMENT
None
Date:
November 15, 1965
Creator:
Hocking, J.E.
System:
The UNT Digital Library
PRELIMINARY DESIGN REPORT-PROTOTYPE STEAM GENERATOR. VOL. 4. SPECIFICATIONS. SODIUM-HEATED STEAM GENERATOR DEVELOPMENT
None
Date:
November 15, 1965
Creator:
unknown
System:
The UNT Digital Library
Protection cup corrosion
None
Date:
November 15, 1965
Creator:
DeZubay, E.A. & Layland, E.
System:
The UNT Digital Library
SNAP aerospace safety program. Progress report, July--September 1965
None
Date:
November 15, 1965
Creator:
Detterman, R.L.
System:
The UNT Digital Library
SNAP systems improvement program. Volume I. Progress report, July-- September 1965
None
Date:
November 15, 1965
Creator:
unknown
System:
The UNT Digital Library
ELECTRODEPOSITION OF ACTINIDES AND LANTHANIDES
None
Date:
December 15, 1965
Creator:
Kim, S.M.; Noakes, J.E.; Akers, L.K. & Miller, W.W.
System:
The UNT Digital Library
Reactor and Materials Technology monthly report 02 Program, November 1965
Metallic fuel development is reported concerning N-reactor fuel element failures, target element development, target element closure welds, alternate target element closure systems, alternate uranium compositions, N-fuel support development, hot die size fuel cladding, improved closures for ThO{sub 2} elements, and N-reactor meltdown tests in the IRP. Corrosion and water quality studies are proceeding with emphasis on downstream pitting of aluminium process tubes, hydride formation in zircaloy tubes, groove and ledge corrosion of aluminium, pitting corrosion of carbon steel in filtered water, storage basin studies, examination of K reactor process tubes, zircaloy tube hydriding studies,nickel plated aluminium, effect of beryllium and uranium on the corrosion of zircaloy-2, and examination of zircaloy-2 graphite cooling tube. Thermal hydraulics studies include boiling burnout experiments for N-reactor and heat transfer experiments for K-reactor. Graphite studies include burnout monitoring in the N-reactor and graphite contraction.
Date:
December 15, 1965
Creator:
Albaugh, F. W.
System:
The UNT Digital Library