TY - GEN
T1 - Composition, structure, manufacture, and properties of sic-sic cmcs for nuclear applications
T2 - Ceramic Materials for Energy Applications VI - 40th International Conference on Advanced Ceramics and Composites, ICACC 2016
AU - Jenkins, Michael G.
AU - Gonczy, Stephen T.
AU - Katoh, Yutai
N1 - Publisher Copyright:
© 2017 by The American Ceramic Society.
PY - 2017
Y1 - 2017
N2 - 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.
AB - 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.
KW - ASME BPVC Section III
KW - NRC
KW - Nuclear reactors
KW - SiC/SiC CMC
UR - http://www.scopus.com/inward/record.url?scp=85044341008&partnerID=8YFLogxK
U2 - 10.1002/9781119321774.ch2
DO - 10.1002/9781119321774.ch2
M3 - Conference contribution
AN - SCOPUS:85044341008
T3 - Ceramic Engineering and Science Proceedings
SP - 17
EP - 22
BT - Ceramic Materials for Energy Applications VI - A Collection of Papers Presented at the 40th International Conference on Advanced Ceramics and Composites, ICACC 2016
A2 - Lin, Hua-Tay
A2 - Matyas, Josef
A2 - Katoh, Yutai
A2 - Vomiero, Alberto
PB - American Ceramic Society
Y2 - 24 January 2016 through 29 January 2016
ER -