SPECIFIC ZIRCONIUM ALLOY DESIGN PROGRAM. First Quarterly Progress Report, February-June 1962

Klepfer, H.H.; Douglass, D. L.; Armijo, J. S.

doi:10.2172/4749877

Cited by 2 publications

(1 citation statement)

References 2 publications

(2 reference statements)

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Zirconium alloys initially did not receive much consideration for these high temperature applications because it was thought that the corrosion rates would be too high, and that the materials would not be strong enough. However earlier work [3][4][5] indicated that some high alloying content Zr alloys showed promise for high temperature corrosion applications.…”

Section: Introductionmentioning

confidence: 99%

Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

Motta

Yilmazbayhan

Silva

et al. 2007

Journal of Nuclear Materials

144

View full text Add to dashboard Cite

Section: Introductionmentioning

confidence: 99%

Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

Motta

Yilmazbayhan

Silva

et al. 2007

Journal of Nuclear Materials

144

View full text Add to dashboard Cite

Microstructure and Properties of a Three-Layer Nuclear Fuel Cladding Prototype Containing Erbium as a Neutronic Burnable Poison

Brachet

Olier

Vandenberghe

et al. 2014

Zirconium in the Nuclear Industry: 17th Volume

View full text Add to dashboard Cite

International audienceTo increase cycle length and/or fuel burnup, several theoretical and experimental studies have been performed at CEA. Among them, prospective neutronic calculations have shown that the addition of a few weight percents of erbium into the cladding materials could be a promising alternative to the introduction of the neutronic poison directly into the nuclear fuel pellets. Thus, fabrication of homogeneous Zr-Er alloys has been assessed, at least up to 10 wt. % of erbium and, based on the as-received mechanical properties, an optimum erbium concentration ranging from 3 to 6 wt. % has been derived. However, because of the high-oxygen thermodynamic affinity of erbium, thermal treatments have to be controlled during the fabrication route to limit Er2O3 precipitation and coarsening, which may have detrimental effects on the ductility/toughness of Zr-Er alloys. In parallel, to get more fundamental insights into the underlying phase diagrams, thermodynamic studies have been devoted to experimental assessment and modeling of the Zr-Er-(H-O) system. Because of the detrimental influence of erbium on the corrosion resistance, a three-layer sandwich clad prototype has been developed using corrosion-resistant inner/outer Zr-1Nb layers to protect the intermediate Zr-Er layer from direct water exposure. Compared to a reference Zr-1Nb(O) alloy that has been subjected to the same fabrication route, the three-layer clad prototype shows limited decrease in ductility because of pre-hydriding or after high-temperature steam oxidation e.g., in the case of a loss-of-coolant accident). Moreover, the studies performed so far have shown a spectacular hydride trapping capacity of the intermediate Zr-Er layer both for hydrogen coming from nominal outer corrosion or because of massive secondary hydriding in case of the direct access of water to the Zr-Er intermediate layer. Using μ-ERDA (elastic recoil detection analysis) measurements, detailed studies of the hydrogen spatial redistribution upon thermal cycling has been done. A simple model has been successfully used to characterize the cooling rate influence on the through-wall clad thickness partitioning of hydrogen/hydrides between the three layers, after cooling from a temperature corresponding to full dissolution of hydride

show abstract

SPECIFIC ZIRCONIUM ALLOY DESIGN PROGRAM. First Quarterly Progress Report, February-June 1962

Cited by 2 publications

References 2 publications

Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

Microstructure and Properties of a Three-Layer Nuclear Fuel Cladding Prototype Containing Erbium as a Neutronic Burnable Poison

Contact Info

Product

Resources

About