TY - GEN
T1 - Hastelloy® N for molten salt reactors used for power generation
AU - Swindeman, Robert W.
AU - Katcher, Michael
AU - Ren, Weiju
AU - Holcomb, David E.
PY - 2017
Y1 - 2017
N2 - Hastelloy® N alloy was developed in the 1950’s as ‘INOR 8’ by the Oak Ridge National Laboratory to resist molten salts used as a fuel and coolant in the early development of molten salt nuclear reactors for propulsion and power generation. China has recently expressed interest in Hastelloy N for use in prototype and demonstration components for a high-temperature, uranium-fueled, molten-salt cooled reactor for the production of electricity. An ASME Section III NH Code Case will be necessary to move Alloy N forward commercially. This paper discusses the guidelines for design data requirements necessary to satisfy the Boiler Code for elevated temperature nuclear applications where creep effects are significant. The historic tensile and creep properties data for Alloy N (N10003) were collected and re-analyzed in accordance with current ASME procedures. The collected data will be uploaded into the ASME Materials Properties Database to support the NH Code Case development.
AB - Hastelloy® N alloy was developed in the 1950’s as ‘INOR 8’ by the Oak Ridge National Laboratory to resist molten salts used as a fuel and coolant in the early development of molten salt nuclear reactors for propulsion and power generation. China has recently expressed interest in Hastelloy N for use in prototype and demonstration components for a high-temperature, uranium-fueled, molten-salt cooled reactor for the production of electricity. An ASME Section III NH Code Case will be necessary to move Alloy N forward commercially. This paper discusses the guidelines for design data requirements necessary to satisfy the Boiler Code for elevated temperature nuclear applications where creep effects are significant. The historic tensile and creep properties data for Alloy N (N10003) were collected and re-analyzed in accordance with current ASME procedures. The collected data will be uploaded into the ASME Materials Properties Database to support the NH Code Case development.
UR - http://www.scopus.com/inward/record.url?scp=85031329256&partnerID=8YFLogxK
U2 - 10.1115/ETAM2014-1036
DO - 10.1115/ETAM2014-1036
M3 - Conference contribution
AN - SCOPUS:85031329256
T3 - ASME 2014 Symposium on Elevated Temperature Application of Materials for Fossil, Nuclear, and Petrochemical Industries, ETAM 2014
BT - ASME 2014 Symposium on Elevated Temperature Application of Materials for Fossil, Nuclear, and Petrochemical Industries, ETAM 2014
PB - American Society of Mechanical Engineers
T2 - ASME 2014 Symposium on Elevated Temperature Application of Materials for Fossil, Nuclear, and Petrochemical Industries, ETAM 2014
Y2 - 25 March 2014 through 27 March 2014
ER -