BEHAVIOR OF MOLYBDENUM IN MIXED-OXIDE FUEL

被引：15

作者：

GIACCHETTI, G ^{[1
]}

SARI, C ^{[1
]}

机构：

[1] EURATOM,INST TRANSURANIUM ELEMENTS,D-7500 KARLSRUHE,FED REP GER

来源：

NUCLEAR TECHNOLOGY | 1976年 / 31卷 / 01期

关键词：

D O I：

10.13182/NT76-A31699

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Metallic molybdenum, Mo-Ru-Rh-Pd alloys, barium, zirconium, and tungsten have been added to uranium and uranium-plutonium oxides by coprecipitation and mechanical mixture techniques. This material has been treated in a thermal gradient similar to that existing in fuel during irradiation to study the behavior of molybdenum in an oxide matrix as a function of the O/(U plus Pu) ratio and some added elements. The result of ceramographic and microprobe analysis shows that when the overall O/(U plus Pu) ratio is less than 2, molybdenum and Mo-Ru-Rh-Pd alloy inclusions are present in the uranium-plutonium oxide matrix. If the O/(U plus Pu) ratio is greater than 2, molybdenum oxidizes to MoO//2, which is gaseous at a temperature about 1000 degree C. Molybdenum oxide vapor reacts with barium oxide and forms a compound that exists as a liquid phase in the columnar grain region. Molybdenum oxide also reacts with tungsten oxide and forms a compound that contains about 40 wt% of actinide metals. The apparent solubility of molybdenum in uranium and uranium-plutonium oxides is determined.

引用

页码：62 / 69

页数：8