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

Kendall, James

Idaho National Laboratory

关键词: Management;    11 - Nuclear Fuel Cycle And Fuel Materials;    Irradiation;    Agr-1;    Fission Products;   

DOI  :  10.2172/911664
RP-ID  :  INL/EXT-06-11487
RP-ID  :  DE-AC07-99ID-13727
RP-ID  :  911664

美国|英语

来源: UNT Digital 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.