TY - GEN
T1 - Achievements of the US-France I-NERI program on heat exchanger alloys for HTR
AU - Cabet, Céline
AU - Wright, Richard
AU - Balbaud-Célérier, Fanny
AU - Rouillard, Fabien
AU - Burlet, Hélène
AU - Gentzbittel, Jean Marie
AU - Lamagnere, Pierre
AU - Dubiez-Legoff, Sophie
AU - Blat, Martine
PY - 2009
Y1 - 2009
N2 - As part of the US Department of Energy bilateral I-NERI initiatives, a 3-year collaborative R&D program has been completed on high temperature nickel base alloys for heat exchangers (IHX) of Generation IV high temperature gas-cooled reactors, named HTR. INL for the US and CEA for France were the leading organizations. The scope was to gain data on the mechanical and corrosion behaviors of Alloy 617 and Alloy 230 in the range of service conditions expected for a high temperature IHX, specifically the temperature, the load and cycling, and the helium impurity content. Main objectives were to compare the performances of both materials and to improve understanding of their properties to help establish the design criteria in terms of: baseline mechanical properties; resistance to creep, fatigue and creep-fatigue; resistance to thermal aging, corrosion and embrittlement. This paper presents the main achievements of that concerted R&D program.
AB - As part of the US Department of Energy bilateral I-NERI initiatives, a 3-year collaborative R&D program has been completed on high temperature nickel base alloys for heat exchangers (IHX) of Generation IV high temperature gas-cooled reactors, named HTR. INL for the US and CEA for France were the leading organizations. The scope was to gain data on the mechanical and corrosion behaviors of Alloy 617 and Alloy 230 in the range of service conditions expected for a high temperature IHX, specifically the temperature, the load and cycling, and the helium impurity content. Main objectives were to compare the performances of both materials and to improve understanding of their properties to help establish the design criteria in terms of: baseline mechanical properties; resistance to creep, fatigue and creep-fatigue; resistance to thermal aging, corrosion and embrittlement. This paper presents the main achievements of that concerted R&D program.
UR - https://www.scopus.com/pages/publications/84907927245
M3 - Conference contribution
AN - SCOPUS:84907927245
T3 - International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
SP - 2360
EP - 2366
BT - International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
PB - Atomic Energy Society of Japan
T2 - International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
Y2 - 10 May 2009 through 14 May 2009
ER -