Optimizing materials for nuclear applications
Conference
·
OSTI ID:5359078
This book presents the papers given at a symposium on materials for fission and fusion reactors. Topics considered at the symposium included liquid metal corrosion, wear-resistant alloys, Zircaloy-2 calandria tubes, the control of microstructure in fuel cans, martensitic stainless steels, austenitic steels, the swelling behavior of stainless steel-316, radiation embrittlement, the aging of iridium and plutonium dioxide, alloying effects on ferritic steels, and void nucleation.
- OSTI ID:
- 5359078
- Report Number(s):
- CONF-840251-
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ABSTRACTS
ACTINIDE COMPOUNDS
AGING
ALLOYS
AUSTENITIC STEELS
CALANDRIAS
CARBON ADDITIONS
CHALCOGENIDES
CHEMICAL REACTIONS
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CONTAINERS
CORROSION
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
DOCUMENT TYPES
ELEMENTS
EMBRITTLEMENT
FERRITIC STEELS
FLUIDS
FUEL CANS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRIDIUM
IRON ADDITIONS
IRON ALLOYS
IRON BASE ALLOYS
LEADING ABSTRACT
LIQUID METALS
LIQUIDS
MARTENSITE
MATERIALS
MECHANICAL PROPERTIES
MEETINGS
METALLURGICAL EFFECTS
METALS
MICROSTRUCTURE
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NUCLEATION
OXIDES
OXYGEN COMPOUNDS
PHYSICAL RADIATION EFFECTS
PLATINUM METALS
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
RADIATION EFFECTS
REACTOR MATERIALS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
SWELLING
THERMONUCLEAR REACTOR MATERIALS
TIN ALLOYS
TRANSITION ELEMENTS
TRANSURANIUM COMPOUNDS
WEAR RESISTANCE
ZIRCALOY
ZIRCALOY 2
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220200* -- Nuclear Reactor Technology-- Components & Accessories
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ABSTRACTS
ACTINIDE COMPOUNDS
AGING
ALLOYS
AUSTENITIC STEELS
CALANDRIAS
CARBON ADDITIONS
CHALCOGENIDES
CHEMICAL REACTIONS
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CONTAINERS
CORROSION
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
DOCUMENT TYPES
ELEMENTS
EMBRITTLEMENT
FERRITIC STEELS
FLUIDS
FUEL CANS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRIDIUM
IRON ADDITIONS
IRON ALLOYS
IRON BASE ALLOYS
LEADING ABSTRACT
LIQUID METALS
LIQUIDS
MARTENSITE
MATERIALS
MECHANICAL PROPERTIES
MEETINGS
METALLURGICAL EFFECTS
METALS
MICROSTRUCTURE
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NUCLEATION
OXIDES
OXYGEN COMPOUNDS
PHYSICAL RADIATION EFFECTS
PLATINUM METALS
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
RADIATION EFFECTS
REACTOR MATERIALS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
SWELLING
THERMONUCLEAR REACTOR MATERIALS
TIN ALLOYS
TRANSITION ELEMENTS
TRANSURANIUM COMPOUNDS
WEAR RESISTANCE
ZIRCALOY
ZIRCALOY 2
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS