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Perspective on 鈥渃ode qualifying鈥� new graphite grades for use in advanced nuclear reactors*

by Anne A Campbell
Publication Type
Journal
Journal Name
Frontiers in Nuclear Engineering
Publication Date
Volume
1
Issue
1

The American Society of Mechanical Engineers (ASME) publishes the Boiler and Pressure Vessel (BPV) Code, which include guidance for the safe development, construction, and operation of boilers and pressure vessels. ASME BPV Code Section III 鈥淩ules for Construction of Nuclear Facility Components鈥� Division 5 focuses on 鈥淗igh Temperature Reactors鈥�. Subsection HH, subpart A lists the different materials properties that are to be measured and how those properties change due to different environmental conditions (oxidation and irradiation damage) for a graphite to be accepted for use in a high temperature reactor core (i.e., 鈥淐ode Qualified鈥�). Currently there are no nuclear graphite grades that are 鈥淐ode Qualified鈥� (i.e., a reactor designer can select a graphite grade and build their reactor without any additional testing), which is due in part to development of new graphite grades in the last 20聽years and the lack of comprehensive programs needed to produce the data for the code cases. This perspective is going to discuss the requirements, as called out in the ASME BPV Code, that are necessary to 鈥渃ode qualify鈥� a nuclear graphite grade but will primarily focus on the practical and technical challenges associated with irradiation-induced property changes and how to address these to assist with getting graphite ready for use in advanced nuclear reactors. These same technical challenges can be expected to arise for other materials being developed for advanced reactor concepts.