Talk:Zirconium alloys

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Zircaloy

The compositions of the alloys list a small amount of hafnium. Is this added on purpose or is this meant to reflect the hafnium impurity in commercial zirconium? If it is the latter, perhaps it should be removed from the formula. --Pyrochem 03:03, 19 February 2007 (UTC)[reply]

zircaloy zircalloy

What I had heard on television had souned like zircoloid, zirculoid; what I found on websites is fuel cladding.

[[ hopiakuta Please do sign your signature on your message. ~~ Thank You. -]] 00:50, 10 March 2008 (UTC)[reply]

redirects

This needs a redirect from zircoloid. 184.144.160.156 (talk) 08:34, 16 March 2011 (UTC)[reply]

Done -- ke4roh (talk) 19:00, 16 March 2011 (UTC)[reply]

Zirconium role in the Fukushima accident

This article is very deficient in regards to the Physical and Chemical properties of the different Zircaloys. In view of the terrible accident in the nuclear plant in Japan, the nuclear technology will have to be revised again in respect to the phenomena that can happen inside a nuclear reactor, therefore, the Zircaloy behaviour in those circumstances has to be presented . Aspects that need to be addressed: Melting point of Zircaloys, reactivity at very elevated temperatures, reactivity towards water vapor and the flammable/explosive Hydrogen generation in a nuclear reactor thermal runaway condition, such as the one observed at Fukushima nuclear power plant in Japan in March 2011. amclaussen. —Preceding unsigned comment added by 192.100.180.20 (talk) 16:06, 17 March 2011 (UTC)[reply]

I have added some explanations dealing with the chemical reaction of zirconium with water steam at high temperature to explain the production of hydrogen in the Fukushima accident. Shinkolobwe (talk) 13:13, 20 March 2011 (UTC)[reply]

The main disadvantage of metallic zirconium is to react with water steam at high temperature. Oxidation by water is accompanied by release of hydrogen gas. This can occur under accidental conditions inside the core of a damaged nuclear reactor if the fuel assemblies are no longer completely covered by liquid water and insufficiently cooled.^[1] Metallic zirconium is then oxidized by the protons of water to form hydrogen gas according to the following redox reaction:

Zr → Zr⁴⁺ + 4 e^–

4 H⁺ + 4 e^– → 2 H₂

Zr + 4 H⁺ → Zr⁴⁺ + 2 H₂

The water reduction by zirconium finally leads to the formation of zirconium oxide or zirconium hydroxide according to the respective global reactions:

Zr + 2 H₂O → ZrO₂ + 2 H₂

Zr + 4 H₂O → Zr(OH)₄ + 2 H₂

This exothermic reaction, although only occurring at high temperature, is similar to that of alkaline metals (such as sodium or potassium) with water. It also closely resembles the anaerobic oxidation of iron by water. Shinkolobwe (talk) 13:17, 20 March 2011 (UTC)[reply]

References

^ Luc Gillon (1979). Le nucléaire en question, Gembloux Duculot, French edition, 240 pp.

References still to fetch and to cite

Go to:

http://www.sciencedirect.com <br\> And run the following querry: <br\> Zirconium hydrogen fuel rod

1,445 articles found.

Buffer of references to cite in the main article:

Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions. State-of-the-art Report. OECD 2009, NEA No. 6846.<br\>https://www.oecd-nea.org/nsd/reports/2009/nea6846_LOCA.pdf

Results from the power burst facility severe fuel damage test 1-4; A simulated severe fuel damage accident with irradiated fuel rods and control rods: <br\>http://www.osti.gov/energycitations/product.biblio.jsp?osti_id=5105109

Reflooding experiments with LWR-type fuel rod simulators in the QUENCH facility: <br\>http://dx.doi.org/10.1016/S0029-5493(00)00308-3

Zirconium oxidation on the atomic scale: <br\>http://dx.doi.org/10.1016/j.ultramic.2008.10.020

Steam oxidation of fuel in defective LWR rods: <br\>http://dx.doi.org/10.1016/S0022-3115(98)00759-4

Chemical processes in defective LWR fuel rods: <br\>http://dx.doi.org/10.1016/S0022-3115(97)00172-4

Shinkolobwe (talk) 13:46, 20 March 2011 (UTC)[reply]

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[1] Luc Gillon (1979). Le nucléaire en question, Gembloux Duculot, French edition, 240 pp.

[1]