The irradiation behavior of atomized U-Mo alloy fuels at high temperature

被引：1

作者：

Park, Jong-Man ^{[2
]}

Kim, Ki-Hwan ^{[2
]}

Kim, Chang-Kyu ^{[2
]}

Meyer, M.K. ^{[1
]}

Hofman, G.L. ^{[1
]}

Strain, R.V. ^{[1
]}

机构：

[1] Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439-4815, United States

[2] Korea Atom. Ener. Research Institute, 150 Dukjin-Dong Yusung-ku, Taejon 305-353, Korea, Republic of

来源：

Metals and Materials International | 2001年 / 7卷 / 02期

关键词：

Irradiation - Binary alloys - Molybdenum alloys - Chemical analysis - Dispersions - Radiation;

D O I：

10.1007/bf03026953

中图分类号：

学科分类号：

摘要：

Post-irradiation examinations of atomized U-10Mo, U-6Mo, and U-6Mo-1.7Os; dispersion fuels from the RERTR-3 experiment irradiated in the Advanced Test Reactor (ATR) were carried out in order to investigate the fuel behavior of high uranium loading (8 gU/cc) at a high temperature (higher than 200°C). It was observed after about 40at% BU that the U-Mo alloy fuels at a high temperature showed similar irradiation bubble morphologies compared to those at a lower temperature found in the RERTR-1 irradation result, but there was a thick reaction layer with the aluminum matrix which was found to be greatly affected by the irradiation temperature and to a lesser degree by the fuel composition. In addition, the chemical analysis for the irradiated U-Mo fuels using the Electron Probe Micro Analysis (EPMA) method were conducted to investigate the compositional changes during the formation of the reaction product.

引用

页码：151 / 157