Feasibility analysis of modified AL-6XN steel for structure component application in supercritical water-cooled reactor
Xinggang LI , Qingzhi YAN , Rong MA , Haoqiang WANG , Changchun GE
Front. Energy ›› 2009, Vol. 3 ›› Issue (2) : 193 -197.
Feasibility analysis of modified AL-6XN steel for structure component application in supercritical water-cooled reactor
Modified AL-6XN austenite steel was patterned after AL-6XN superaustenitic stainless steel by introducing microalloy elements such as zirconium and titanium in order to adapt to recrystallizing thermo-mechanical treatment and further improve crevice corrosion resistance. Modified AL-6XN exhibited comparable tensile strength, and superior plasticity and impact toughness to commercial AL-6XN steel. The effects of aging behavior on corrosion resistance and impact toughness were measured to evaluate the qualification of modified AL-6XN steel as an in-core component and cladding material in a supercritical water-cooled reactor. Attention should be paid to degradation in corrosion resistance and impact toughness after aging for 50 hours when modified AL-6XN steel is considered as one of the candidate materials for in-core components and cladding tubes in supercritical water-cooled reactors.
supercritical water cooled reactor / tensile / impact toughness / corrosion / aging
| [1] |
U.S. DOE Nuclear Energy Research Advisory Committee (NERAC) and the Generation IV International Forum (GIF). A technology roadmap for generation IV nuclear energy systems.<patent> GIF-002-00</patent><OrgAddress> Washington D C</OrgAddress> 2002 |
| [2] |
|
| [3] |
|
| [4] |
Allegheny Ludlum Corporation. Stainless steel AL-6XN alloy. UNS Designation N08367. Technical Data Blue Sheet, Pittsburgh, PA, 1998 |
| [5] |
|
Higher Education Press and Springer-Verlag Berlin Heidelberg
/
| 〈 |
|
〉 |