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Title: Testing of Small Graphite Samples for Nuclear Qualification

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.
Authors:
Publication Date:
OSTI Identifier:
1009170
Report Number(s):
INL/EXT-10-20275
TRN: US1101747
DOE Contract Number:
DE-AC07-05ID14517
Resource Type:
Technical Report
Research Org:
Idaho National Laboratory (INL)
Sponsoring Org:
DOE - NE
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; GRAIN SIZE; GRAPHITE; MECHANICAL PROPERTIES; MONITORING; TENSILE PROPERTIES; TEST REACTORS; TESTING; graphite