Abstract
The tensile strength distribution of graphite has historically been estimated via the two- and three-parameter Weibull distributions due to the flaw distribution within the material. This is apparent within the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III “Rules for Construction of Nuclear Facility Components”, Division 5 “High Temperature Reactors”, Subsection HH “Class SN Nonmetallic Core Components”, Subpart A “Graphite Materials”, where the materials data sheet (MDS) requires the calculation of both the two- and three-parameter Weibull distributions of the tensile strength for as-manufactured graphite. There is not currently a requirement to determine Weibull distribution of the strength of graphite post-irradiation, mainly because no results have been reported that suggest whether the Weibull parameters, most importantly the Weibull modulus, changes due to neutron irradiation damage. An irradiation program was performed at Oak Ridge National Laboratory where graphite grade ETU-10 was exposed to neutron damage at a range of temperatures and final neutron fluences. Within this experiment, ten strength coupons were irradiated at each temperature and fluence combination which when analyzed can provide information as to whether irradiation damage has altered the Weibull modulus. This paper will focus on the analysis of the post-irradiated equibiaxial flexural strength change via a Weibull analysis of each individual data set and discussion as to whether there appears to be statistically significant changes to the Weibull parameters.
Original language | English |
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Title of host publication | Codes and Standards; Computer Technology and Bolted Joints |
Publisher | American Society of Mechanical Engineers (ASME) |
ISBN (Electronic) | 9780791888476 |
DOIs | |
State | Published - 2024 |
Event | ASME 2024 Pressure Vessels and Piping Conference, PVP 2024 - Bellevue, United States Duration: Jul 28 2024 → Aug 2 2024 |
Publication series
Name | American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP |
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Volume | 1 |
ISSN (Print) | 0277-027X |
Conference
Conference | ASME 2024 Pressure Vessels and Piping Conference, PVP 2024 |
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Country/Territory | United States |
City | Bellevue |
Period | 07/28/24 → 08/2/24 |
Funding
This research was sponsored by the U.S. Department of Energy, Office of Nuclear Energy Advanced Reactor Technology Program. The data analyzed for this work was a result of a research effort sponsored by IBIDEN Co., Ltd. under the Material Science and Technology Division, Work-for-Others (WFO) Program, DOE agreement: NFE-11-03389, with the U.S. Department of Energy. A portion of this research used resources at the High Flux Isotope Reactor, a DOE Office of Science User Facility operated by the Oak Ridge National Laboratory. Oak Ridge National Laboratory is managed by UT-Battelle, LLC, under contract No. DE-AC05-00OR22725 for the U.S. Department of Energy.
Keywords
- ASME Code Qualification
- Irradiation effects
- Nuclear graphite
- Weibull statistics