[go: up one dir, main page]

Greenfield, 1964 - Google Patents

A comparison of Magnox A 12 and ZA alloys as canning materials for nuclear reactors

Greenfield, 1964

Document ID
8034191818450992658
Author
Greenfield P
Publication year
Publication venue
Journal of Nuclear Materials

External Links

Snippet

The properties of the magnesium alloys ZA and A 12 are compared for their use as fuel element canning materials in power reactors of the Calder Hall type. It is concluded that ZA shows more resistance to grain growth than A 12 and also possesses superior mechanical …
Continue reading at www.sciencedirect.com (other versions)

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • Y02E30/40Other aspects relating to nuclear fission
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • Y02E30/38Fuel
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • G21C3/07Casings; Jackets characterised by their material, e.g. alloys
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E60/00Enabling technologies or technologies with a potential or indirect contribution to GHG emissions mitigation

Similar Documents

Publication Publication Date Title
EP0326896B1 (en) Nuclear fuel element having oxidation resistant cladding
US4718949A (en) Method of producing a cladding tube for reactor fuel
US5373541A (en) Nuclear fuel rod and method of manufacturing the cladding of such a rod
US5519748A (en) Zircaloy tubing having high resistance to crack propagation
KR920009645B1 (en) Zirconium base fuel cladding resistant to pci crack propagation
US4675153A (en) Zirconium alloy fuel cladding resistant to PCI crack propagation
US4775508A (en) Zirconium alloy fuel cladding resistant to PCI crack propagation
JPH0790522A (en) Production of zircaloy pipe excellent in resistance to crack growth
US5073336A (en) Corrosion resistant zirconium alloys containing copper, nickel and iron
EP0399222A1 (en) Corrosion resistant zirconium alloys containing copper, nickel and iron
US9378850B2 (en) Method for operating a nuclear reactor and use of a specific fuel rod cladding alloy in order to reduce damage caused by pellet/cladding interaction
Fleck et al. Pressure Tube Development for
Grossbeck et al. Irradiation creep in type 316 stainless steel and US PCA with fusion reactor He/dpa levels
US7127024B2 (en) Fuel element for a pressurized water reactor
Erbacher et al. A review of zircaloy fuel cladding behavior in a loss-of-coolant accident
EP0195155B1 (en) Water reactor fuel cladding tubes
Greenfield A comparison of Magnox A 12 and ZA alloys as canning materials for nuclear reactors
US5267290A (en) Zirconium alloy absorber layer
Stahl Fuels for research and test reactors, status review: July 1982
Cheadle et al. High-strength, creep-resistant excel pressure tubes
EP0194797A1 (en) Water reactor fuel element cladding tube
US3440140A (en) Protection of zirconium alloy components against hydriding
EP0745258B1 (en) A nuclear fuel element for a pressurized water reactor and a method for manufacturing the same
US3567581A (en) Uranium-silicon fuel elements for a nuclear reactor
Pickman Zirconium alloy performance in light water reactors: a review of UK and Scandinavian experience