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

被引：27

作者：

Park, JM

Kim, KH

Kim, CK

Meyer, MK

Hofman, GL

Strain, RV

机构：

[1] Korea Atom Energy Res Inst, Yusung Ku, Taejon 305353, South Korea

[2] Argonne Natl Lab, Argonne, IL 60439 USA

来源：

METALS AND MATERIALS-KOREA | 2001年 / 7卷 / 02期

关键词：

RERTR; ATR; post-irradiation; atomized U-Mo dispersion fuel; fuel behavior; high temperature irradiation;

D O I：

10.1007/BF03026953

中图分类号：

T [工业技术];

学科分类号：

08 ;

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 degreesC). It was observed after about 40 at% 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 irradiation 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

页数：7