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zircaloy alloys
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Series: ASM Handbook
Volume: 9
Publisher: ASM International
Published: 01 December 2004
DOI: 10.31399/asm.hb.v09.a0003782
EISBN: 978-1-62708-177-1
... some examples of the microstructure and examination for zircaloy alloys, hafnium, zirconium, and bimetallic forms. chemical processing applications etching grinding hafnium hafnium alloys metallography microstructure mounting nuclear applications polishing sectioning specimen...
Abstract
Zirconium, hafnium, and their alloys are reactive metals used in a variety of nuclear and chemical processing applications. This article describes various specimen preparation procedures for these materials, including sectioning, mounting, grinding, polishing, and etching. It reviews some examples of the microstructure and examination for zircaloy alloys, hafnium, zirconium, and bimetallic forms.
Book Chapter
Series: ASM Desk Editions
Publisher: ASM International
Published: 01 December 1998
DOI: 10.31399/asm.hb.mhde2.a0003149
EISBN: 978-1-62708-199-3
... up to 4.5% Hf. Properly speaking, the alloy names Zircaloy and Zr-2.5Nb apply to nuclear-grade materials. The most common zirconium alloys, Zircaloy-2 and Zircaloy-4, contain the strong α stabilizers tin and oxygen, plus the β stabilizers iron, chromium, and nickel. There is an extensive α + β...
Abstract
This article discusses the general characteristics, primary and secondary fabrication methods, product forms, and corrosion resistance of zirconium and hafnium. It describes the physical metallurgy of zirconium and its alloys, providing details on allotropic transformation and anisotropy that profoundly influences the engineering properties of zirconium and its alloys. Tables listing the values for chemical composition and tensile properties for nuclear and nonnuclear grades of zirconium are also provided.
Series: ASM Handbook
Volume: 13C
Publisher: ASM International
Published: 01 January 2006
DOI: 10.31399/asm.hb.v13c.a0004148
EISBN: 978-1-62708-184-9
... been studied, and two major families remain: the Zircaloys, that is, Zr-Sn-O (+Fe, Cr, Ni) alloys, and the Zr-Nb-O alloys (with 1 and 2.5 wt% Nb). Advanced ternary and quaternary alloys are currently under development for higher-performance industrial alloys. Characteristics of water reactor fuel...
Abstract
The components used in light water reactors (LWR) often remain in contact with the primary coolant, whose typical temperatures and pressures are highly aggressive, therefore, initiating corrosion in most of the alloys. This article describes the corrosion behavior of zirconium alloys in water and heat flow conditions that causes irradiation on the zirconium alloy assemblies. It discusses the effect of irradiation on the microstructure and morphology of cladded linings. The article describes the impact of metallurgical parameters on the oxidation resistance of zirconium alloys. It concludes with a discussion on LWR coolant chemistry and corrosion of fuel rods in reactors.
Image
in Metallography and Microstructures of Zirconium, Hafnium, and Their Alloys
> Metallography and Microstructures
Published: 01 December 2004
. The micrographs show a Zircaloy as-cast structure with twinning and alloy variation, as exhibited by different preparation methods. Original magnification: 1000×.
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Series: ASM Handbook
Volume: 2
Publisher: ASM International
Published: 01 January 1990
DOI: 10.31399/asm.hb.v02.a0001084
EISBN: 978-1-62708-162-7
... levels were finally reduced below 1000 ppm, it was found that required strength levels in Zircaloy could no longer be met. The status of oxygen then changed to one of a controlled solid-solution alloying agent. Early methods for determining oxygen content were crude and relatively imprecise, so hardness...
Abstract
Zirconium, hafnium, and titanium are produced from ore that generally is found in a heavy beach sand containing zircon, rutile, and ilmenite. This article discusses the processing methods of these metals, namely, liquid-liquid separation process, distillation separation process, refining, and melting. It also discusses the primary and secondary fabrication of zirconium and hafnium and its alloys. The article talks about the metallurgy of zirconium and its alloys with emphasis on allotropic transformation, cold work and recrystallization, anisotropy and preferred orientation, and the role of oxygen. It concludes by providing useful information on the applications of reactor and industrial grades of zirconium alloys.
Series: ASM Handbook
Volume: 6
Publisher: ASM International
Published: 01 January 1993
DOI: 10.31399/asm.hb.v06.a0001441
EISBN: 978-1-62708-173-3
... alloys, as specified in ASTM B 550, are given in Table 1 . For reactor grades, the hafnium content is reduced to a minimum and other impurities are closely controlled. Chemical compositions of the most common grades of nuclear-grade Zircaloys, as specified in ASTM B 351, are given in Table 2...
Abstract
Zirconium and its alloys are available in two general categories: commercial grade and reactor grade. This article discusses the welding processes that can be used for welding any of the zirconium alloys. These include gas-tungsten arc welding (GTAW), gas-metal arc welding (GMAW), plasma arc welding (PAW), electron-beam welding (EBW), laser-beam welding (LBW), friction welding (FRW), resistance welding (RW), resistance spot welding (RSW), and resistance seam welding (RSEW). The article reviews the selection of shielding gases and filler metals for welding zirconium alloys. It concludes with a discussion on process procedures for welding zirconium alloys.
Book: Surface Engineering
Series: ASM Handbook
Volume: 5
Publisher: ASM International
Published: 01 January 1994
DOI: 10.31399/asm.hb.v05.a0001312
EISBN: 978-1-62708-170-2
... by a chemical bath of nitric-hydrofluoric acid is used most commonly, although other baths have been used. The usual bath for zirconium, Zircaloys, and hafnium is composed of 25 to 50% nitric acid, 70 vol%; 2 to 5% hydrofluoric acid, 49 vol%; and the remainder water. The acid bath for zirconium-niobium alloys...
Abstract
Zirconium and hafnium surfaces require cleaning and finishing for reasons such as preparation for joining, heat treatment, plating, forming, and producing final surface finishes. This article provides information on various surface treatment processes, surface soil removal, blast cleaning, chemical descaling, pickling or etching, anodizing, autoclaving, polishing, buffing, vapor phase nitriding, and electroplating. Applications of these surface treatment processes are also reviewed.
Image
in Metallography and Microstructures of Zirconium, Hafnium, and Their Alloys
> Metallography and Microstructures
Published: 01 December 2004
Fig. 4 Zircaloy 4 tube, longitudinal. (a) Mid-thickness. (b) Near surface, attack polished, etchant procedure No. 6 ( Table 2 ), differential interference contrast. These micrographs show the difference in alloy variation between mid-thickness and near-surface locations. Original magnification
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Book: Corrosion: Materials
Series: ASM Handbook
Volume: 13B
Publisher: ASM International
Published: 01 January 2005
DOI: 10.31399/asm.hb.v13b.a0003823
EISBN: 978-1-62708-183-2
... revealed that tin was the most beneficial alloying element. The Zr-2.5-Sn alloy was named Zircaloy-1 and was recommended for the Nautilus reactor. By 1952, data showed that Zircaloy-1 had an increasing rate of corrosion over time. An urgent search for a new alloy began. Fortunately, Bettis Atomic...
Abstract
This article provides a description of the classification, industrial applications, microstructures, physical, chemical, corrosion, and mechanical properties of zirconium and its alloys. It discusses the formation of oxide films and the effects of water, temperature, and pH on zirconium. The delayed hydride cracking of zirconium is also described. The article provides information on the resistance of zirconium to various types of corrosion, including pitting corrosion, crevice corrosion, intergranular corrosion, galvanic corrosion, microbiologically induced corrosion, erosion-corrosion, and fretting corrosion. The article explains the effects of tin content in zirconium and effects of fabrication on corrosion. Corrosion control measures for all types of corrosion are also highlighted. The article concludes with information on the safety precautions associated with handling of zirconium.
Series: ASM Handbook
Volume: 13A
Publisher: ASM International
Published: 01 January 2003
DOI: 10.31399/asm.hb.v13a.a0003635
EISBN: 978-1-62708-182-5
... required to initiate a crack or by cladding with a high-purity metal of the alloy that is embrittled but that has a very low yield stress. Thus, Zircaloy, which is clad with a high-purity zirconium, becomes immune to embrittlement by cadmium. The obvious possibility is to replace embrittling liquid metals...
Abstract
Liquid metal induced embrittlement (LMIE) is the reduction of the fracture resistance of a solid material during exposure to a liquid metal. This article discusses the mechanisms and occurrence condition of LMIE and describes the effects of metallurgical factors, such as grain size, temperature and strain rate, stress, inert carriers, and fatigue, on LMIE. It provides a detailed discussion on LMIE in ferrous and nonferrous metals and their alloys. In addition, the article highlights the ways of preventing embrittlement in metals and alloys.
Series: ASM Handbook
Volume: 13C
Publisher: ASM International
Published: 01 January 2006
DOI: 10.31399/asm.hb.v13c.a0004223
EISBN: 978-1-62708-184-9
... Mid-1970s PWSCC of PWR alloy 600 steam generator tubing Mid-1970s Pellet-cladding interaction failures of BWR zircaloy fuel cladding Mid-1970s IGSCC of BWR welded small-diameter type 304 piping Mid-1970s IGSCC of BWR large-diameter type 304 piping Late 1970s IGSCC of BWR alloy X-750...
Abstract
This article reviews a series of serious corrosion problems that have plagued the light water reactor (LWR) industry. It discusses the complex corrosion mechanisms involved, and the development of practical engineering solutions for their mitigation. The article contains tables that present the corrosion history of LWRs, and the ten most expensive operation and maintenance costs of corrosion for a particular reactor site.
Series: ASM Handbook
Volume: 13A
Publisher: ASM International
Published: 01 January 2003
DOI: 10.31399/asm.hb.v13a.a0003636
EISBN: 978-1-62708-182-5
... in this Section. Although SMIE of metals has not been mentioned or recognized as an embrittlement phenomenon in industrial processes, many instances of loss in ductility, strength, and brittle fracture of metals and alloys have been reported for electroplated metals and coatings or inclusions of low-melting...
Abstract
Embrittlement that occurs below the melting point of the embrittling species is known as solid metal induced embrittlement (SMIE) of metals. This article provides a discussion on the characteristics and investigations of SMIE, liquid metal induced embrittlement, and delayed failure. It also describes the mechanism of SMIE.
Book: Corrosion: Materials
Series: ASM Handbook
Volume: 13B
Publisher: ASM International
Published: 01 January 2005
DOI: 10.31399/asm.hb.v13b.a0003826
EISBN: 978-1-62708-183-2
... of hafnium in high-temperature water Material Weight gain, mg/dm 2 28 days 56 days Zircaloy (a) 20–22 25–28 Hafnium 3–6 5–7 (b) (a) Nuclear grade of zirconium containing iron, chromium, nickel, and tin as important alloy additions. (b) Estimated range; test not run...
Abstract
This article describes the processes involved in the production of hafnium and its alloys. It discusses the physical, mechanical and chemical properties of hafnium. The aqueous corrosion testing of hafnium and its alloys is detailed. The article reviews the corrosion resistance of hafnium in specific media, namely, water, steam, hydrochloric acid, nitric acid, sulfuric acid, alkalis, organics, molten metals, and gases. Forms of corrosion, namely, galvanic corrosion, crevice corrosion, and pitting corrosion are included. The article explains the corrosion of hafnium alloys such as hafnium-zirconium alloys and hafnium-tantalum alloys. It also deals with the applications of hafnium and its alloys in the nuclear and chemical industries.
Series: ASM Handbook
Volume: 13C
Publisher: ASM International
Published: 01 January 2006
DOI: 10.31399/asm.hb.v13c.a0004147
EISBN: 978-1-62708-184-9
... Abstract This article examines the understanding of persistent material changes produced in stainless alloys during light water reactor (LWR) irradiation based on the fundamentals of radiation damage and existing experimental measurements. It summarizes the overall trends and correlations...
Abstract
This article examines the understanding of persistent material changes produced in stainless alloys during light water reactor (LWR) irradiation based on the fundamentals of radiation damage and existing experimental measurements. It summarizes the overall trends and correlations for irradiation-assisted stress-corrosion cracking. The article addresses the effects of various radiation factors on corrosion. These include radiation-induced segregation at grain boundaries, radiation hardening, mode of deformation, radiation creep relaxation, and radiolysis. The article discusses a variety of approaches for mitigating stress-corrosion cracking in LWRs, in categories of water chemistry, operating guidelines, new alloys, design issues, and stress mitigation. It concludes with a discussion on the irradiation effects of irradiation on corrosion of zirconium alloys in LWR environments.
Series: ASM Handbook
Volume: 22A
Publisher: ASM International
Published: 01 December 2009
DOI: 10.31399/asm.hb.v22a.a0005418
EISBN: 978-1-62708-196-2
... and Texture Development of Polycrystals: Application to Zirconium Alloys , Acta Metall. Mater. , Vol 41 ( No. 9 ), 1993 , p 2611 – 2624 8. Turner P.A. and Tomé C.N. , A Study of Residual Stresses in Zircaloy-2 with Rod Texture , Acta Metall. Mater. , Vol 42 ( No. 12 ), 1994 , p...
Abstract
Self-consistent models are a particular class of models in continuum micromechanics, that is, the field concerned with making predictions of the properties and evolution of aggregates whose single-crystal deformation behavior is known. This article provides information on the measurement and representation of textures as well as prediction of texture evolution in single-phase materials and two-phase aggregates.
Book Chapter
Series: ASM Handbook
Volume: 9
Publisher: ASM International
Published: 01 December 2004
DOI: 10.31399/asm.hb.v09.a0003748
EISBN: 978-1-62708-177-1
...–10 s Zirconium, Zr-2 1 2 %Nb alloy, Zircaloy-2, Zircaloy-4, Hafnium 45 mL NHO 3 45 mL water 8–10 mL HF Use as above Zirconium, Hafnium 45 mL H 2 O 2 (30%) 45 mL HNO 3 8–10 mL HF Use as above Zircaloy-2, Hafnium 70 mL water 30 mL HNO 3 2–5 mL HF Use as above Zr-Cr-O...
Abstract
Metallographic preparation of a material involves the elimination of artifacts or scratches from fine polishing and may be achieved by methods such as attack polishing, vibratory polishing, chemical polishing, electrolytic polishing, and electromechanical polishing. This article discusses the mechanism, operating procedure, advantages, and limitations of chemical and electrolytic polishing of samples for metallographic preparation. It provides information on the specimen preparation, apparatus used, and safety precautions to be followed during the polishing process. The various groups of electrolytes used in electropolishing of several metals and alloys are reviewed. The article concludes with a discussion on local electropolishing.
Book Chapter
Series: ASM Handbook
Volume: 9
Publisher: ASM International
Published: 01 December 2004
DOI: 10.31399/asm.hb.v09.a0003764
EISBN: 978-1-62708-177-1
.... Continue 5–10 s. Cain Zirconium, Zr-2 1 2 % Nb alloy, Zircaloy-2, Zircaloy-4, and hafnium 45 mL NHO 3 45 mL H 2 O 8–10 mL HF Use as above. Cain Zirconium and hafnium 45 mL H 2 O 2 (30%) 45 mL HNO 3 8–10 mL HF Use as above. Cain Zircaloy-2 and hafnium 70 mL H 2 O 30 mL HNO 3 2...
Abstract
This article is a comprehensive collection of tables listing: dangerous reactions of chemicals and designations of etchants; chemical-polishing solutions for irons and steels and nonferrous materials; attack-polishing solutions, macrostructure etchants for iron and steel; and major microstructure etchants for common phases and constituents in ferrous materials.
Series: ASM Handbook
Volume: 6
Publisher: ASM International
Published: 01 January 1993
DOI: 10.31399/asm.hb.v06.a0001456
EISBN: 978-1-62708-173-3
... corrosion resistance of most zirconium applications, and testing in the proposed use environment is compulsory. Brazing filler alloys that have demonstrated acceptable pressurized hot-water corrosion properties after 1450 h at 360 °C (680 °F) include Zr-5Be, Cu-20Pd-3In, and Ni-20Pd-10Si. Zircaloy...
Abstract
This article provides a discussion on filler metal selection, brazing procedures, and brazing equipment for brazing refractory metals. These include molybdenum, tungsten, niobium, and tantalum, and reactive metals. Commercially pure and alpha titanium alloys, alpha-beta alloys, zirconium alloys, and beryllium alloys are some reactive metals discussed in the article.
Series: ASM Handbook
Volume: 6
Publisher: ASM International
Published: 01 January 1993
DOI: 10.31399/asm.hb.v06.a0001384
EISBN: 978-1-62708-173-3
... 0.51 0.020 1690 ± 335 380 ± 80 0.64 0.025 1910 ± 220 430 ± 50 Tantalum … 0.25 0.010 1110 ± 135 250 ± 30 Titanium alloy Ti-5Al-2.5Sn 0.71 0.028 8670 ± 535 1950 ± 120 Ti-8Mn 0.81 0.032 7690 ± 890 1730 ± 200 Ti-6Al-4V 1.02 0.040 10005 ± 800 2260 ± 180 Zircaloy-2...
Abstract
This article begins with a discussion on the advantages and limitation of ultrasonic welding (USW). It describes variations of the USW process which can produce different weld geometries. These variations are helpful in producing spot welds, line welds, continuous seam welds, ring welds, and microelectronic welds. The article provides information on the functions of USW personnel and describes the special conditions in USW which include the condition of the surface, the use of an interlayer, and the control of resonance. It concludes with a description on the weld quality, the influencing factors, surface appearance and deformation, and metallographic examination.
Book Chapter
Series: ASM Desk Editions
Publisher: ASM International
Published: 01 December 1998
DOI: 10.31399/asm.hb.mhde2.a0003145
EISBN: 978-1-62708-199-3
... stabilizers in zirconium alloys and enhance high-temperature strength. A commercial series of corrosion-resistant zirconium alloys (Zircaloys) containing 0.15 to 2.5% Sn has been developed for nuclear service. Powder Applications Much of the supply of tin powders is used in making sintered bronze...
Abstract
Tin is a soft, brilliant white, low-melting metal that is most widely known and characterized in the form of coating. This article discusses the primary and secondary production of tin and explains the uses of tin in coating, namely tinplating, electroplating, and hot dip coatings. It presents a short note on pure (unalloyed) tin and uses of tin in chemicals. The article also covers the compositions and uses of tin alloys which include solders, pewter, bearing alloys, alloys for organ pipes, and fusible alloys. It goes on to discuss the other alloys containing tin including battery grid alloys, type metals, copper alloys, dental alloys, cast irons, titanium alloys, and zirconium alloys. Finally, it presents a short note on the applications of tin powder and corrosion resistance of tin.
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