科技报告详细信息
AGC-1 Irradiation Experiment Test Plan.
Bratton, R. L.
Technical Information Center Oak Ridge Tennessee
关键词: Nuclear reactors;    Irradiation;    Creep;    Graphite;    Mechanical properties;   
RP-ID  :  DE2008911702
学科分类:工程和技术(综合)
美国|英语
来源: National Technical Reports Library
PDF
【 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 degrees 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.

【 预 览 】
附件列表
Files Size Format View
DE2008911702.pdf 542KB PDF download
  文献评价指标  
  下载次数:12次 浏览次数:6次