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Helium profiles across fast reactor fuel pin cladding

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7338217
 [1]; ; ;
  1. Atomics International, Canoga Park, CA
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None
OSTI ID:
7338217
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 23
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYOGENIC FLUIDS
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FISSION PRODUCTS
FLUIDS
FUEL CANS
FUEL ELEMENTS
HEAT RESISTING ALLOYS
HELIUM
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NONMETALS
RADIOACTIVE MATERIALS
RARE GASES
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TEST REACTORS