AGR-1 Irradiation--Objectives, Success Criteria and Risk Management.

Kendall, J. M.

Technical Information Center Oak Ridge Tennessee

关键词: Enriched uranium;    Irradiation;    Fission products;    Burnup;    Irradiation devices;   

RP-ID  :  DE2008911664

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

The AGR-1 experiment being conducted by the US Department of Energy Advanced Gas Reactor Fuel Development and Qualification Program (AGR fuel program) will irradiate TRISO-coated particle fuel in compacts under conditions representative of a Very High Temperature Reactor (VHTR) core. The anticipated fuel performance requirements of a prismatic core VHTR significantly exceed established TRISO-coated particle fuel capability in terms of burnup, temperature and fast fluence. AGR-1 is the first in a planned series of eight irradiations leading to the qualification of low enriched uranium coated particle fuel compacts for service in a VHTR, as identified in an overall Technical Program Plan produced at the beginning of the program . The AGR-1 experiment is scheduled for insertion in the Advanced Test Reactor (ATR) in the first quarter of fiscal year 2007 and to be irradiated for a period of up to approximately two and a half years. The irradiation rig, designated a 'test train' is designed to provide six independently controlled (for temperature) and monitored (for fission product gas release) capsules containing fuel samples.