SPECIFIC ZIRCONIUM ALLOY DESIGN PROGRAM. Summary Report

Klepfer, H.H.

doi:10.2172/4672662

Cited by 5 publications

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“…Klepfer et al [40] developed the Zr-1.1 %Cr-0.1 %Fe alloy (Valoy), Tyzack et al [41] described the SCANUK alloys and the Zr-Cu-Fe--Mo-V alloys were studied in former Czechoslovakia [42]. Klepfer et al [40] developed the Zr-1.1 %Cr-0.1 %Fe alloy (Valoy), Tyzack et al [41] described the SCANUK alloys and the Zr-Cu-Fe--Mo-V alloys were studied in former Czechoslovakia [42].…”

Section: Alloys For Applications In Steam At 500 °Cmentioning

confidence: 99%

Corrosion of Zr Alloys in Water and Steam

1994

Materials Science Monographs

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The oxide, Zr0 2 , is formed by the reaction of Zr with water. Water molecules dissociate on the oxide surface, the oxygen formed diffuses through anion vacancies in the oxide to the metal-oxide boundary, where part of the oxygen dissolves in the metal and part reacts to form new oxide. As the oxide has a greater volume than the metal from which it was formed, strain is produced at the boundary. Hydrogen formed in the reaction partly diffused through the oxide into the metal.The process of oxidation of Zr and its alloys in water and steam passes through several stages with correspondingly different laws for the rate of oxide growth as a function of temperature and the corrosion exposure time. In the initial stage, especially at low temperatures, the oxide growth has a complex character, controlled by either a logarithmic or parabolic rate law. This period is a result of localized oxidation of the grain boundaries and of intermetallic species, preferential oxidation of some grains, etc.At temperatures above 300 °C, the oxidation rate is controlled by a cubic or parabolic law. Black, adhering and non-stoichiometric Zr0 2 is also formed. After a certain period of time, given by the oxidation conditions, a change occurs in the oxidation kinetics, appearing as a break on the kinetic curves, after which the oxidation kinetics obey a linear law. This is mostly accompanied by the formation of white or light grey (light brown) oxide, that adheres poorly to the metal and peels off.The increase in the mass of the Zr alloys sample with time can be expressed by the relationship ΔΜ = kt n (9.1)where Am is the mass increase per unit surface area, t is the oxidation time, k is the oxidation rate constant, and n is a dimensionless coefficient. The corrosion process is affected by a great many factors, the most important of which are: the chemical composition of the Zr alloy, both alloying elements and impurities in the metal, the metal structure determined by the technology of alloy working, the quality of the alloy surface, determined by the technology, the composition of the corrosive medium, the influence of radiation, especially the flux and the fluence of fast neutrons. 9.

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Section: Alloys For Applications In Steam At 500 °Cmentioning

confidence: 99%

Corrosion of Zr Alloys in Water and Steam

1994

Materials Science Monographs

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“…However, a controlled experiment revealed the corrosion performance of Zr-Cr was not specially sensitive to nitrogen, and the commercial specification for nitrogen in the Zircaloys was also adequate for Zr-Cr. ( 6 ) With this background, it was postulated that the nonuniform distribution of intermetallics in the first round tubing was caused by segregation of chromium in the beta-phase during fabrication in the two-phase temperature region. Since all fabrication steps, Figure 2-3, after extrusion were performed at temperatures below 760° C, it is unlikely the precipitate coarsening occurred during or after extrusion.…”

Section: {5)mentioning

confidence: 99%

THE FABRICATION AND CHARACTERIZATION OF Zr--Cr ALLOY TUBING.

Busboom¹,

Cleveland²,

Klepfer³

et al. 1968

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To expe dite dis~-•.nati on of tech nica l info rmat ion to thos e pers o;;r ~Y. 1ng it, this repo rt has been issu ed /;""'~ z ~ • ,.. • with out-j 1ID..a .-•••. i'str. ative rev iew nece ssar y t prot ect ..-/,..-&. the i nter.# es •of the u.s. ,6oy er,.nm ent, th~ Euro pean .,. / / / / .... ; j\tow iC/ Ene rgy Com mun ity (};ur atom) i n he con-/. ' /-~. / ' ' ~-: tra ctor. The recip iet1t '0: this repo rt-agr-e e ""~ at it is pass ed on to him in conf iden ce"' that he will main tain that conf iden ce and mak e,., n •"" < e-l~su res or publ icati on of the cont ents , th.i,(5v_9~t e detr imen tal to-th e in-..... ~ tere sts of__t !J~ U". ST .:_Y ernm erit, the Euro pean Atom ic Ener gy :.Com fuug, ity"'(Eura tom) and the cont racto r .

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Work hardening and ductility of Zr-1.14% Cr-0.1% Fe

Holt

1974

Journal of Nuclear Materials

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SPECIFIC ZIRCONIUM ALLOY DESIGN PROGRAM. Summary Report

Cited by 5 publications

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Corrosion of Zr Alloys in Water and Steam

Corrosion of Zr Alloys in Water and Steam

THE FABRICATION AND CHARACTERIZATION OF Zr--Cr ALLOY TUBING.

Work hardening and ductility of Zr-1.14% Cr-0.1% Fe

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