SE8301815D0 - Zirconium alloy barriers with improved corrosion resistance - Google Patents

Zirconium alloy barriers with improved corrosion resistance

Info

Publication number
SE8301815D0
SE8301815D0 SE8301815A SE8301815A SE8301815D0 SE 8301815 D0 SE8301815 D0 SE 8301815D0 SE 8301815 A SE8301815 A SE 8301815A SE 8301815 A SE8301815 A SE 8301815A SE 8301815 D0 SE8301815 D0 SE 8301815D0
Authority
SE
Sweden
Prior art keywords
zirconium alloy
substrate
dilute
corrosion resistance
zirconium
Prior art date
Application number
SE8301815A
Other languages
Swedish (sv)
Other versions
SE8301815L (en
SE462307B (en
Inventor
R B Adamson
Original Assignee
Gen Electric
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Gen Electric filed Critical Gen Electric
Publication of SE8301815D0 publication Critical patent/SE8301815D0/en
Publication of SE8301815L publication Critical patent/SE8301815L/en
Publication of SE462307B publication Critical patent/SE462307B/en

Links

Classifications

    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B32—LAYERED PRODUCTS
    • B32B—LAYERED PRODUCTS, i.e. PRODUCTS BUILT-UP OF STRATA OF FLAT OR NON-FLAT, e.g. CELLULAR OR HONEYCOMB, FORM
    • B32B15/00—Layered products comprising a layer of metal
    • B32B15/01—Layered products comprising a layer of metal all layers being exclusively metallic
    • 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
    • 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
    • G21C3/16—Details of the construction within the casing
    • G21C3/20—Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
    • 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 GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Metallurgy (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Plasma & Fusion (AREA)
  • Organic Chemistry (AREA)
  • Laminated Bodies (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Separation Using Semi-Permeable Membranes (AREA)
  • Chemically Coating (AREA)
  • Physical Vapour Deposition (AREA)
  • Other Surface Treatments For Metallic Materials (AREA)

Abstract

ZIRCONIUM ALLOY BARRIER HAVING IMPROVED CORROSION RESISTANCE A nuclear fuel element for use in the core of a nuclear reactor which has a composite cladding container having a substrate and a dilute zirconium alloy liner bonded to the inside surface of the substrate. The dilute zirconium alloy liner forms about 1 to about 20 percent of the thickness of the cladding and comprises from about 0.1% to about 0.5% by weight niobium and preferably from about 0.2% to about 0.4% by weight niobium, the balance being zirconium. The dilute zirconium alloy liner shields the substrate from impurities or fissin products from the nuclear fuel material and protects the substrate from stress corrosion and stress cracking. The dilute zirconium alloy liner displays greater corrosion resistance, especially to oxidation by hot water and steam than unalloyed zirconium. The substrate material is selected from conventional cladding materials, and preferably is a zirconium alloy having a higher alloy content than the dilute zirconium alloy liner.
SE8301815A 1982-03-31 1983-03-30 Nuclear fuel elements with composite casing containers and composite casing containers with zirconium alloy cladding SE462307B (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US36395682A 1982-03-31 1982-03-31

Publications (3)

Publication Number Publication Date
SE8301815D0 true SE8301815D0 (en) 1983-03-30
SE8301815L SE8301815L (en) 1983-10-01
SE462307B SE462307B (en) 1990-05-28

Family

ID=23432437

Family Applications (1)

Application Number Title Priority Date Filing Date
SE8301815A SE462307B (en) 1982-03-31 1983-03-30 Nuclear fuel elements with composite casing containers and composite casing containers with zirconium alloy cladding

Country Status (7)

Country Link
JP (1) JPS58195185A (en)
BE (1) BE896318A (en)
CA (1) CA1198231A (en)
DE (1) DE3310054A1 (en)
ES (1) ES8605119A1 (en)
IT (1) IT1160767B (en)
SE (1) SE462307B (en)

Families Citing this family (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5958389A (en) * 1982-09-29 1984-04-04 日本核燃料開発株式会社 Nuclear fuel element
US4664881A (en) * 1984-03-14 1987-05-12 Westinghouse Electric Corp. Zirconium base fuel cladding resistant to PCI crack propagation
US4675153A (en) * 1984-03-14 1987-06-23 Westinghouse Electric Corp. Zirconium alloy fuel cladding resistant to PCI crack propagation
US4613479A (en) * 1984-03-14 1986-09-23 Westinghouse Electric Corp. Water reactor fuel cladding
US4775508A (en) * 1985-03-08 1988-10-04 Westinghouse Electric Corp. Zirconium alloy fuel cladding resistant to PCI crack propagation
JPS61217793A (en) * 1985-03-08 1986-09-27 ウエスチングハウス・エレクトリック・コ−ポレ−ション Nuclear fuel coated tube
US4933136A (en) * 1985-03-08 1990-06-12 Westinghouse Electric Corp. Water reactor fuel cladding
CN86101123A (en) * 1985-03-08 1987-01-21 西屋电气公司 Vessel of water reactor fuel
JPS6224182A (en) * 1985-03-08 1987-02-02 ウエスチングハウス・エレクトリック・コ−ポレ−ション Nuclear fuel coated tube
ES2023983B3 (en) * 1987-07-21 1992-02-16 Siemens Ag FUEL ROD FOR A NUCLEAR REACTOR COMBUSTION ELEMENT
US4894203A (en) * 1988-02-05 1990-01-16 General Electric Company Nuclear fuel element having oxidation resistant cladding
US4971753A (en) * 1989-06-23 1990-11-20 General Electric Company Nuclear fuel element, and method of forming same
SE513185C2 (en) † 1998-12-11 2000-07-24 Asea Atom Ab Zirconium-based alloy and component of a nuclear power plant

Also Published As

Publication number Publication date
ES8605119A1 (en) 1986-02-16
SE8301815L (en) 1983-10-01
IT8320296A0 (en) 1983-03-25
JPH033917B2 (en) 1991-01-21
JPS58195185A (en) 1983-11-14
BE896318A (en) 1983-09-30
SE462307B (en) 1990-05-28
DE3310054A1 (en) 1983-10-13
CA1198231A (en) 1985-12-17
ES520223A0 (en) 1986-02-16
IT1160767B (en) 1987-03-11

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