SODIUM-COOLED REACTORS FAST CERAMIC REACTOR DEVELOPMENT PROGRAM. Thirty- Ninth Quarterly Report, May--July 1971.
- Research Organization:
- General Electric Co., Sunnyvale, Calif. Breeder Reactor Dept.
- DOE Contract Number:
- AT(04-3)-189
- NSA Number:
- NSA-26-055189
- OSTI ID:
- 4615832
- Report Number(s):
- GEAP-10028-39
- Resource Relation:
- Other Information: UNCL. Orig. Receipt Date: 31-DEC-72
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
N78150* -Power Reactor Development-Fuel Systems & Components
N50140 -Metals
Ceramics
& Other Materials-Ceramics & Cermets-Radiation Effects
N50240 -Metals
Ceramics
& Other Materials-Metals & Alloys-Radiation Effects
DEFECTS- FAST NEUTRONS- FUEL CANS- FUEL ELEMENTS- INCOLOY- MECHANICAL PROPERTIES- PLUTONIUM OXIDES- RADIATION EFFECTS- STAINLESS STEEL- 316- STAINLESS STEEL-321- STAINLESS STEEL-347- SWELLING- URANIUM DIOXIDE
DESIGN
FBR TYPE REACTORS
FLUID FLOW
FUEL ELEMENTS
LIQUID METALS
LOSS OF COOLANT
PERFORMANCE TESTING
REACTOR CORES
REACTOR KINETICS
REACTOR SAFETY
SODIUM
SODIUM COOLED REACTORS
TRANSIENTS EBR-2 REACTOR- FUEL CANS- FUEL ELEMENTS- IRRADIATION- PLUTONIUM OXIDES- SODIUM COOLED REACTORS- STAINLESS STEELS- URANIUM DIOXIDE
URANIUM OXIDES UO$sub 2$/PuO$sub 2$-UO$sub 2$
radiation effects testing of fuels of
STAINLESS STEEL/radiation effects on swelling and mechanical properties of Type 316, Type 321, and Type 347, fast neutron, (E)
INCOLOY 800/radiation effects on swelling and mechanical properties of
fast neutron
(E)
NEUTRONS, FAST/effects on Incoloy 800 and stainless steels Type 316, Type 321, and Type 347
PLUTONIUM OXIDES PuO$sub 2$/PuO$sub 2$-UO$sub 2$
radiation effects testing of fuels of
FAST CERAMIC REACTOR/fuel elements for
development during May to July 1971
FAST CERAMIC REACTOR/safety of
transient overpower and coolant flow loss effects on
REACTOR FUEL ELEMENTS/ performance of defected mixed plutonium oxide (PuO$sub 2$)-uranium oxide (UO$sub 2$) fast
in flowing liquid sodium
URANIUM OXIDES UO$sub 2$/PuO$sub 2$-UO$sub 2$, properties of fuels of, mechanical, physical, and thermal, (E)
EXPERIMENTAL BREEDER REACTOR-II/fuel irradiation testing in
status of mixed oxide
LIQUID META
N50140 -Metals
Ceramics
& Other Materials-Ceramics & Cermets-Radiation Effects
N50240 -Metals
Ceramics
& Other Materials-Metals & Alloys-Radiation Effects
DEFECTS- FAST NEUTRONS- FUEL CANS- FUEL ELEMENTS- INCOLOY- MECHANICAL PROPERTIES- PLUTONIUM OXIDES- RADIATION EFFECTS- STAINLESS STEEL- 316- STAINLESS STEEL-321- STAINLESS STEEL-347- SWELLING- URANIUM DIOXIDE
DESIGN
FBR TYPE REACTORS
FLUID FLOW
FUEL ELEMENTS
LIQUID METALS
LOSS OF COOLANT
PERFORMANCE TESTING
REACTOR CORES
REACTOR KINETICS
REACTOR SAFETY
SODIUM
SODIUM COOLED REACTORS
TRANSIENTS EBR-2 REACTOR- FUEL CANS- FUEL ELEMENTS- IRRADIATION- PLUTONIUM OXIDES- SODIUM COOLED REACTORS- STAINLESS STEELS- URANIUM DIOXIDE
URANIUM OXIDES UO$sub 2$/PuO$sub 2$-UO$sub 2$
radiation effects testing of fuels of
STAINLESS STEEL/radiation effects on swelling and mechanical properties of Type 316, Type 321, and Type 347, fast neutron, (E)
INCOLOY 800/radiation effects on swelling and mechanical properties of
fast neutron
(E)
NEUTRONS, FAST/effects on Incoloy 800 and stainless steels Type 316, Type 321, and Type 347
PLUTONIUM OXIDES PuO$sub 2$/PuO$sub 2$-UO$sub 2$
radiation effects testing of fuels of
FAST CERAMIC REACTOR/fuel elements for
development during May to July 1971
FAST CERAMIC REACTOR/safety of
transient overpower and coolant flow loss effects on
REACTOR FUEL ELEMENTS/ performance of defected mixed plutonium oxide (PuO$sub 2$)-uranium oxide (UO$sub 2$) fast
in flowing liquid sodium
URANIUM OXIDES UO$sub 2$/PuO$sub 2$-UO$sub 2$, properties of fuels of, mechanical, physical, and thermal, (E)
EXPERIMENTAL BREEDER REACTOR-II/fuel irradiation testing in
status of mixed oxide
LIQUID META