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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...
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...
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...
Image
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×. More
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...
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...
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...
Image
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 More
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...
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...
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...
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...
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...
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...
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...
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...
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...
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...
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...
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...