Ells et al., 1964 - Google Patents
Development of zirconium-niobium alloysElls et al., 1964
View PDF- Document ID
- 11544777474496992389
- Author
- Ells C
- Dalgaard S
- Evans W
- Thomas W
- Publication year
External Links
Snippet
f Third United Nations International Conference on the Peaceful Uses of Atomic Energy Page 1
r f Third United Nations International Conference on the Peaceful Uses of Atomic Energy
Confidential until official release during Conference A/C0NF.28/P/22 CANADA May 1964 …
- 229910001257 Nb alloy 0 title abstract description 22
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
-
- 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
- C22F1/16—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of other metals or alloys based thereon
- C22F1/18—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of other metals or alloys based thereon high-melting or refractory metals 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
- 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
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
- Y02E30/40—Other aspects relating to nuclear fission
-
- 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
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US6811746B2 (en) | Zirconium alloy having excellent corrosion resistance and mechanical properties for nuclear fuel cladding tube | |
EP0910098A2 (en) | Zirconium niobium tin alloys for nuclear fuel rods and structural parts for high burnup | |
EP2647732B1 (en) | Precipitation-strengthened ni-based heat-resistant alloy and method for producing the same | |
KR930009987B1 (en) | Method of manufacturing tubes of zirconium alloys with improved corrosion resistance for thermal nuclear reactors | |
US4360389A (en) | Zirconium alloy heat treatment process | |
KR100411943B1 (en) | Zirconium-based alloy tube for a nuclear reactor fuel assembly and a process for producing such a tube | |
US3271205A (en) | Zirconium base alloys | |
US5854818A (en) | Zirconium tin iron alloys for nuclear fuel rods and structural parts for high burnup | |
US5844959A (en) | Zirconium niobium tin alloys for nuclear fuel rods and structural parts for high burnup | |
Urbanic et al. | Effect of microstructure on the corrosion of Zr-2.5 Nb alloy | |
Ells et al. | Development of zirconium-niobium alloys | |
US5835550A (en) | Method of manufacturing zirconium tin iron alloys for nuclear fuel rods and structural parts for high burnup | |
EP0076110B1 (en) | Maraging superalloys and heat treatment processes | |
US10119181B2 (en) | Treatment process for a zirconium alloy, zirconium alloy resulting from this process and parts of nuclear reactors made of this alloy | |
Klepfer | Zirconium—niobium binary alloys for boiling water reactor service part I—corrosion resistance | |
US3341373A (en) | Method of treating zirconium-base alloys | |
CA1080513A (en) | Zirconium alloy heat treatment process and product | |
US4359349A (en) | Method for heat treating iron-nickel-chromium alloy | |
KR20240163984A (en) | Chemical compositions of Beta-Ti based neutron absorbing structural materials with excellent neutron absorption capability, strength and ductility, and the neutron absorbing materials manufactured through the same | |
Oliveira et al. | Hydrogen kinetics and hydride formation effect on Zr-1Nb and Zr-1Nb-1Sn-0.1 Fe alloys for nuclear application | |
Kittel et al. | Effect of irradiation on fuel materials | |
Schemel | Effect of Heat Treatment on the Structure, Mechanical Properties, and Corrosion Resistance of Heavy Forged Sections of Zircaloy-2 | |
US3431104A (en) | Zirconium base alloy | |
US3804680A (en) | Method for inducing resistance to embrittlement by neutron irradiation and products formed thereby | |
EP0745258B1 (en) | A nuclear fuel element for a pressurized water reactor and a method for manufacturing the same |