Cermet fuel in a light water reactor: a possible way to improve safety. Part II. Testing the fuel

详细信息	查看全文 | 推荐本文 |

• 作者：Troyanov ; V. ; Popov ; V. ; Baranaev ; Iu.
• 关键词：nuclear fuel ; cermet ; property ; testing
• 刊名：Progress in Nuclear Energy
• 出版年：2001
• 期刊代码：42_01491970
• 类别：pw
• 出版时间：2001
• 卷：38
• 期：3-4
• 页码：383-386
• 文件大小：262 K

摘要

This paper summarizes what is done for the experimental testing of cermet fuel with various matrix materials. Low neutron absorption, high heat conductivity, good corrosion resistance in water, low chemical interaction with cladding (zirconium alloy) and UO₂ in normal and accident conditions, technological ability — are the requirements of the matrix material [1]. Suitability of the proposed solutions to the cermet fuel design with respect to these requirements was proven through a series of experiments simulating fuel operating and accidental conditions.