Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
7965439 | Journal of Nuclear Materials | 2015 | 30 Pages |
Abstract
A mixed ceramic composite composed of UO2-UN was studied to increase both the thermal conductivity and uranium density of the currently used UO2 pellet. UN powder was synthesized by hydriding and then nitriding spherical U metal powders. Disk-shaped mixed UO2-UN composites were fabricated by hot pressing UO2-UN powder mixtures within a temperature range of 1300 °C-1590 °C. A phase analysis was conducted using X-ray diffraction and a SEM analysis indicated that the sintered composite consists mainly of a mixture of UO2 and UN phases. Compared to pure UO2, the UO2-33vol% UN composite showed an increase in uranium density of 13% (10.91 g/cm3) and an increase in thermal conductivity of up to 100% (8.16 W/m k at 800 °C).
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
Jae Ho Yang, Dong-Joo Kim, Keon Sik Kim, Yang-Hyun Koo,