Testing of Small Graphite Samples for Nuclear Qualification

Chapman, Julie

Idaho National Laboratory

关键词: Tensile Properties;    Mechanical Properties;    Monitoring;    Grain Size;    22 General Studies Of Nuclear Reactors;   

DOI  :  10.2172/1009170
RP-ID  :  INL/EXT-10-20275
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1009170

美国|英语

来源: UNT Digital Library

【 摘 要 】

Accurately determining the mechanical properties of small irradiated samples is crucial to predicting the behavior of the overal irradiated graphite components within a Very High Temperature Reactor. The sample size allowed in a material test reactor, however, is limited, and this poses some difficulties with respect to mechanical testing. In the case of graphite with a larger grain size, a small sample may exhibit characteristics not representative of the bulk material, leading to inaccuracies in the data. A study to determine a potential size effect on the tensile strength was pursued under the Next Generation Nuclear Plant program. It focuses first on optimizing the tensile testing procedure identified in the American Society for Testing and Materials (ASTM) Standard C 781-08. Once the testing procedure was verified, a size effect was assessed by gradually reducing the diameter of the specimens. By monitoring the material response, a size effect was successfully identified.