Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

Motta, Arthur T.; Yilmazbayhan, Aylin; Silva, Marcelo José Gomes da; Comstock, R. J.; Was, Gary S.; Busby, Jeremy T.; Gärtner, Eric; Peng, Qunjia; Jeong, Yong Hwan; Park, Jeong Yong

doi:10.1016/j.jnucmat.2007.05.022

Cited by 145 publications

(49 citation statements)

References 15 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…The structure of the oxide-metal interface is of great interest to understanding the mechanism of oxide growth and the differences between the protective and non-protective oxides. As it was demonstrated in [10][11][12], the protective alloys always exhibit extra peaks in the diffraction scans obtained near the oxide-metal interface region. These peaks have been associated with two different phases found in that region in the protective oxides:…”

Section: Suboxides Of Zirconiummentioning

confidence: 58%

“…As it will be demonstrated below with atomistic simulations, the formation of certain oxygen bearing zirconium compounds, especially monoclinic ZrO 2 and suboxide Zr 3 O [10][11][12], at the interface "cooling wateralloy surface" is critical to preventing hydrogen pickup. Under normal working conditions the primary source of hydrogen is radiolysis of water.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

Glazoff¹

2013

View full text Add to dashboard Cite

Zirconium-based alloys Zircaloy-2 and Zircaloy-4 are widely used in the nuclear industry as cladding materials for light water reactor (LWR) fuels. These materials display a very good combination of properties such as low neutron absorption, creep behavior, stress-corrosion cracking resistance, reduced hydrogen uptake, corrosion and/or oxidation, especially in the case of Zircaloy-4. However, over the last couple of years, in the post-Fukushima Daiichi world, energetic efforts have been undertaken to improve fuel clad oxidation resistance during off-normal temperature excursions. Efforts have also been made to improve upon the already achieved levels of mechanical behavior and reduce hydrogen uptake. In order to facilitate the development of such novel materials, it is very important to achieve not only engineering control, but also a scientific understanding of the underlying material degradation mechanisms, both in working conditions and in storage of used nuclear fuel.This report strives to contribute to these efforts by constructing the thermodynamic models of both alloys; constructing of the respective phase diagrams, and oxidation mechanisms. A special emphasis was placed upon the role of zirconium suboxides in hydrogen uptake reduction and the atomic mechanisms of oxidation. To that end, computational thermodynamics calculations were conducted concurrently with first-principles atomistic modeling.

show abstract

Section: Suboxides Of Zirconiummentioning

confidence: 58%

Section: Introductionmentioning

confidence: 99%

Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

Glazoff¹

2013

View full text Add to dashboard Cite

show abstract

“…Copper additions in Zr-base alloys, tend to be observed mainly as a tetragonal Zr 2 Cu phase [34], even though the complete phase diagram presents a large number of possible intermetallic compounds [35,36].…”

Section: Crystallography Of Intermetallic Phasesmentioning

confidence: 99%

Hydrogen solubility in zirconium intermetallic second phase particles

Burr

Murphy

Lumley

et al. 2013

Journal of Nuclear Materials

View full text Add to dashboard Cite

The enthalpies of solution of H in Zr binary intermetallic compounds formed with Cu, Cr, Fe, Mo, Ni, Nb, Sn and V were calculated by means of density functional theory simulations and compared to that of H in α-Zr. It is predicted that all Zr-rich phases (formed with Cu, Fe, Ni and Sn), and those phases formed with Nb and V, offer lower energy, more stable sites for H than α-Zr. Conversely, Mo and Cr containing phases do not provide preferential solution sites for H. In all cases the most stable site for H are those that offer the highest coordination fraction of Zr atoms. Often these are four Zr tetrahedra but not always. Implications with respect to H-trapping properties of commonly observed ternary phases such as Zr(Cr,Fe) 2 , Zr 2 (Fe,Ni) and Zr(Nb,Fe) 2 are also discussed.

show abstract

“…Selain itu, niobium yang ditambahkan ke dalam paduan berbasis zirkonium berfungsi untukmemperhalus ukuran butir sehingga dapat meningkatkan kekuatan mekanik paduan [4,5] . Besi (Fe) dan khrom (Cr) yang ditambahkan sebagai unsur pemadu digunakan untuk meningkatkan kekuatan mekanik yang ditandai dengan terbentuknya presipitat Zr(Fe, Cr)2 yang keras di dalam paduan zirkonium [6] . Penambahan unsur Nb, Fe dan Cr tidak berpengaruh secara signifikan terhadap ekonomi neutron termal karena tampang lintang serapan neutron termalnya rendah.…”

Section: Pendahuluanunclassified

PENGARUH PENGEROLAN PANAS TERHADAP KARAKTER PADUAN Zr-0,6Nb-0,5Fe-0,5Cr

Sungkono

Aidah

2016

urania

View full text Add to dashboard Cite

ABSTRAKPENGARUH PENGEROLAN PANAS TERHADAP KARAKTER PADUAN Zr-0,6Nb-0,5Fe-0,5Cr. Paduan Zr-0,6Nb-0,5Fe-0,5Cr hasil pengerolan panas telah diteliti karakternya. Tujuan penelitian ini adalah mendapatkan data pengaruh pengerolan panas terhadap karakteristik mikrostruktur, kekerasan dan fasa yang terbentuk dalam paduan Zr-0,6Nb-0,5Fe-0,5Cr. Proses pengerolan panas paduan Zr-0,6Nb-0,5Fe-0,5Cr dilakukan pada temperatur 800 o C dengan waktu penahanan (soaking time) 1,5 dan 2 jam dan reduksi ketebalan 5-25 %. Hasil penelitian menunjukkan bahwa paduan Zr-0,6Nb-0,5Fe-0,5Cr memiliki struktur Widmanstätten dengan evolusi mikrostruktur menjadi kolumnar terdeformasi dan batang pipih terdeformasi seiring dengan semakin besarnya reduksi ketebalan. Selain itu, semakin lama waktu penahanan pada temperatur 800 o C maka ukuran butir relatif lebih besar dan terjadi pembentukan fasa -Zr dan Zr3Fe. Kekerasan paduan Zr-0,6Nb-0,5Fe-0,5Cr mempunyai kecenderungan yang sama yaitu semakin besar reduksi ketebalan maka semakin tinggi kekerasannya. Paduan Zr-0,6Nb-0,5Fe-0,5Cr mampu menerima deformasi besar berupa pengerolan panas dengan reduksi ketebalan 25 % dan terbentuknya fasa -Zr dan Zr3Fe dapat meningkatkan kekerasan dan kekuatan paduan Zr-0,6Nb-0,5Fe-0,5Cr.Kata kunci: Paduan, pengerolan panas, reduksi ketebalan, mikrostruktur, kekerasan, fasa.

show abstract

Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

Cited by 145 publications

References 15 publications

Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

Hydrogen solubility in zirconium intermetallic second phase particles

PENGARUH PENGEROLAN PANAS TERHADAP KARAKTER PADUAN Zr-0,6Nb-0,5Fe-0,5Cr

Contact Info

Product

Resources

About