Composition, structure, manufacture, and properties of sic-sic cmcs for nuclear applications: Informational chapters in the asme bpv code section III

Future nuclear reactors planned by US DOE will use SiC/SiC CMCs to enhance fuel performance and improve accident tolerance. SiC/SiC CMCs are tolerant to the irradiation and chemical environments of current and future nuclear reactors. Because SiC/SiC CMCs are nonconventional materials, a concern with these plans involves the mission of the US Nuclear Regulatory Commission (NRC) which is to license and regulate the nation’s civilian use of byproduct, sources and special nuclear materials. Note that the NRC regulates nuclear reactors and new reactor design as well as the reactor materials. The NRC not only imploys, but is legally required to use, consensus codes and standards as an integral part of the regulatory process. In particular, the ASME Boiler and Pressure Vessel Code (BPVC) Section III “Rules for Construction of Nuclear Components” (which codifies and standardizes acceptable materials for nuclear applications) is included in the NRC regulations. Therefore, for SiC/SiC CMCs to be incorporated into current and future nuclear reactors, they must be included in ASME BPVC as acceptable materials. This presentation provides an overview of two informational chapters regarding the composition, structure, manufacture, and properties of SiC/SiC CMCs for nuclear applications as currently being developed in ASME BPVC Section III.