Session: CS-15-01 Mechanical Properties of Nuclear Graphite and Their Implementation in Codes and Standards (Joint with MF-29) – 1

Paper Number: 106610

106610 - Development of a Graphite Irradiation Qualification Plan for the Xe-100 Reactor 

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”, has a list of materials properties that must be measured and included in the materials data sheet (MDS) for each grade of graphite to be used in a reactor core.  Two sections of the MDS includes measuring the effects of degradation, due to oxidation or neutron irradiation damage, on these materials properties.  A program at Oak Ridge National Laboratory (ORNL), supported by X Energy, LLC., began in 2017 to produce the irradiation-induced property change results of graphite grades that will be used in the X Energy Xe-100 small modular reactor.  Significant effort has been performed around the world to capture these property changes for a range of graphite grades through both the US Advanced Graphite Creep program, and the EU INNOGRAPH/ARCHER program.  But both programs were primarily targeted towards higher temperature reactor designs that were of greater importance at the beginning of both programs resulting in a lack of data for temperatures below 600°C.  The program at ORNL has been developed to produce the data necessary to assist with completing the irradiation effects on materials properties of the MDS for the graphite grades of interest for X Energy.  This paper will discuss the design of the irradiation program including the irradiation conditions (neutron fluence and irradiation temperatures), the types of specimens being used in this program, and the irradiation methodology.

Presenting Author: Anne Campbell Oak Ridge National Laboratory

Presenting Author Biography: Dr. Anne Campbell is research associate in the Materials Science and Technology Division at Oak Ridge National Laboratory. She was awarded her Ph.D., under the supervision of Prof. Gary S. Was, from the University of Michigan’s Nuclear Engineering and Radiological Sciences department in 2014. She joined ORNL in 2014 as a post-doctoral research associate and transitioned to full-time staff in 2016. Dr. Campbell’s research focuses on understanding the effects of irradiation, and other extreme environmental conditions, on materials properties. Her current research activities include understanding the effects of irradiation, high temperature, and stress (irradiation creep) on the materials properties of graphite and other carbon-based materials, irradiation creep of steels, and development of novel materials for advanced nuclear applications. Dr. Campbell is active in multiple professional organizations including The Minerals, Metals & Materials Society (TMS), the American Nuclear Society (ANS), the American Ceramics Society (ACerS), the American Society for Testing Materials (ASTM), and the American Society of Mechanical Engineers (ASME). Outside of work Dr. Campbell enjoys spending time with her partner, two daughters, and the family's retired greyhound.

Authors:

Anne Campbell Oak Ridge National Laboratory
Josina Geringer Oak Ridge National Laboratory
Adrian Schrell Oak Ridge National Laboratory
Samuel Baylis X Energy, LLC.
Timothy Lucas X Energy, LLC.
Peter Pappano TRISO X, LLC.
Martin Van Staden X Energy, LLC.