Thermoelectric properties of ZrC, UC-ZrC, and UC-UN at 285?450�K

Gomozov, L. I.; Akhmedzyanov, I. Sh.

doi:10.1007/bf01126272

Cited by 3 publications

(2 citation statements)

References 2 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Comparing the lower C containing sample images with the ZrC 1.1 and ZrC 1.2 images (Images E, F, G and H in Figure 5), it is shown that more "crack-like" second phases are present along the grain boundaries and inside of individual grains than the ZrC 0.9 and ZrC 1.0 . This phenomenon is likely attributed to the increase in the C content for these samples [22] [23]. Figure 6 shows EDS elemental maps from ZrC 1.2 which illustrates that grain boundaries are enriched with carbides (graphite).…”

Section: Semmentioning

confidence: 99%

Irradiation-induced effects of proton irradiation on zirconium carbides with different stoichiometries

Huang

Maier

Allen

2014

Nuclear Engineering and Design

View full text Add to dashboard Cite

Zirconium carbide (ZrC) is being considered for utilization in deep burn TRISO fuel particles for high-temperature, gas-cooled reactors. Zirconium carbide has a cubic B1 type crystal structure along with a very high melting point (3420°C), exceptional hardness and good thermal and electrical conductivities. Understanding the ZrC irradiation response is crucial for establishing ZrC as an alternative component in TRISO fuel. Until now, very few studies on irradiation effects on ZrC have been released and fundamental aspects of defect evolution and kinetics are not well understood although some atomistic simulations and phenomenological studies have been performed. This work was carried out to understand the damage evolution in floatzone refined ZrC with different stoichiometries. Proton irradiations at 800°C up to doses of 3dpa were performed on ZrC x (where x ranges from 0.9 to 1.2) to investigate the damage evolution. The irradiation-induced defects, such as density of dislocation loops, at different stoichiometries and doses which were characterized by transmission electron microscopy (TEM) is presented and discussed.

show abstract

Section: Semmentioning

confidence: 99%

Irradiation-induced effects of proton irradiation on zirconium carbides with different stoichiometries

Huang

Maier

Allen

2014

Nuclear Engineering and Design

View full text Add to dashboard Cite

show abstract

“…After 4 Mev Au ion irradiation at room temperature, Gosset has also shown a moderate swelling and high internal stress which both saturate at a Au fluence around 10 14 cm À2 corresponding to a few dpa, and there is a high density of small faulted dislocations revealed by TEM [16]. In addition, the properties of ZrC are often sensitive to the stoichiometry [17,18] and the irradiation behavior are very likely related to the C/Zr ratio, as reported by Andrievskii, the sub-stoichiometric materials damaged relatively less than the nearly-stoichiometric ones under the neutron irradiation in a large stoichiometric range [19]. In summary, the limited neutron and heavy ion exposures are insufficient to fully understand the microstructural stability of ZrC under radiation.…”

Section: Introductionmentioning

confidence: 96%