AGC-1 Irradiation Experiment Test Plan

Bratton, R. L.

Idaho National Laboratory

关键词: Mechanical Properties;    Irradiation;    Vhtr;    Neutrons;    Graphite;   

DOI  :  10.2172/911702
RP-ID  :  INL/EXT-06-11102
RP-ID  :  DE-AC07-99ID-13727
RP-ID  :  911702

美国|英语

来源: UNT Digital Library

【 摘 要 】

The Advanced Graphite Capsule (AGC) irradiation test program supports the acquisition of irradiated graphite performance data to assist in the selection of the technology to be used for the VHTR. Six irradiations are planned to investigate compressive creep in graphite subjected to a neutron field and obtain irradiated mechanical properties of vibrationally molded, extruded, and iso-molded graphites for comparison. The experiments will be conducted at three temperatures: 600, 900, and 1200°C. At each temperature, two different capsules will be irradiated to different fluence levels, the first from 0.5 to 4 dpa and the second from 4 to 7 dpa. AGC-1 is the first of the six capsules designed for ATR and will focus on the prismatic fluence range.