Zinkle et al., 2000 - Google Patents
Operating temperature windows for fusion reactor structural materialsZinkle et al., 2000
View PDF- Document ID
- 12632757092363701277
- Author
- Zinkle S
- Ghoniem N
- Publication year
- Publication venue
- Fusion Engineering and design
External Links
Snippet
A critical analysis is presented of the operating temperature windows for nine candidate fusion reactor structural materials: four reduced-activation structural materials (oxide- dispersion-strengthened and ferritic/martensitic steels containing 8–12% Cr, V–4Cr–4Ti, and …
- 239000000463 material 0 title abstract description 93
Classifications
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C19/00—Alloys based on nickel or cobalt
- C22C19/03—Alloys based on nickel or cobalt based on nickel
- C22C19/05—Alloys based on nickel or cobalt based on nickel with chromium
- C22C19/058—Alloys based on nickel or cobalt based on nickel with chromium without Mo and W
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C19/00—Alloys based on nickel or cobalt
- C22C19/007—Alloys based on nickel or cobalt with a light metal (alkali metal Li, Na, K, Rb, Cs; earth alkali metal Be, Mg, Ca, Sr, Ba, Al Ga, Ge, Ti) or B, Si, Zr, Hf, Sc, Y, lanthanides, actinides, as the next major constituent
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22F—CHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
- C22F1/00—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
- C22F1/10—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of nickel or cobalt or alloys based thereon
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C16/00—Alloys based on zirconium
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C38/00—Ferrous alloys, e.g. steel alloys
- C22C38/18—Ferrous alloys, e.g. steel alloys containing chromium
- C22C38/40—Ferrous alloys, e.g. steel alloys containing chromium with nickel
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C45/00—Amorphous alloys
- C22C45/04—Amorphous alloys with Ni or Co as the major constituent
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C14/00—Alloys based on titanium
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C1/00—Making alloys
Similar Documents
Publication | Publication Date | Title |
---|---|---|
Zinkle et al. | Operating temperature windows for fusion reactor structural materials | |
Rieth et al. | Behavior of tungsten under irradiation and plasma interaction | |
Carroll et al. | Functionally graded material of 304L stainless steel and inconel 625 fabricated by directed energy deposition: Characterization and thermodynamic modeling | |
Field et al. | Handbook on the material properties of FeCrAl alloys for nuclear power production applications | |
Tavassoli | Present limits and improvements of structural materials for fusion reactors–a review | |
Yun et al. | Current state and prospect on the development of advanced nuclear fuel system materials: A review | |
Smith et al. | Vanadium-base alloys for fusion first-wall/blanket applications | |
Rieth et al. | Recent progress in research on tungsten materials for nuclear fusion applications in Europe | |
Northwood et al. | Hydrides and delayed hydrogen cracking in zirconium and its alloys | |
Field et al. | Handbook on the Material Properties of FeCrAl Alloys for Nuclear Power Production Applications (FY18 Version: Revision 1) | |
Prasanthi et al. | Explosive cladding and post-weld heat treatment of mild steel and titanium | |
Yamamoto et al. | Handbook of the materials properties of FeCrAl alloys for nuclear power production applications | |
Zinkle | Evaluation of high strength, high conductivity CuNiBe alloys for fusion energy applications | |
Busby et al. | Radiation-damage in molybdenum–rhenium alloys for space reactor applications | |
Rebak et al. | Resistance of Ferritic FeCrAl alloys to stress corrosion cracking for light water reactor fuel cladding applications | |
Zinkle et al. | Radiation effects in refractory alloys | |
Fenici et al. | Properties of Cr-Mn austenitic stainless steels for fusion reactor applications | |
Itoh et al. | Mechanical properties of overaluminized MCrAlY coatings at room temperature | |
Veeman et al. | Additive manufacturing and characterization of titanium wall used in nuclear application | |
Bowling et al. | A unified model of tensile and creep deformation for use in niobium alloy materials selection and design for high-temperature applications | |
Lei et al. | Determination of Mechanical Properties and Fracture Behavior of Hot-Rolled Inconel 617/Ni Bimetal Composite Plate | |
Prasanthi et al. | Optimization of Heat Treatments for Reversion of Strain-Induced Martensite in 304L SS Explosive Clad | |
Ningshen et al. | Corrosion resistance of 9-15% Cr ODS steels and its comparison with austenitic stainless steel | |
Braski | Microstructure and bend ductility of a (Fe, Ni) 3V ordered alloy irradiated in HFIR | |
Sergienko et al. | Effect of heat treatment on the mechanical properties of Ti–Nb–Mo–Zr–Al alloys |