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http://dx.doi.org/10.3795/KSME-A.2013.37.9.1127

Development of User Subroutine Program Considering Effect of Neutron Irradiation on Mechanical Material Behavior of Austenitic Stainless Steels  

Kim, Jong Sung (Dept. of Mechanical Engineering, Sunchon Nat'l Univ.)
Jhung, Myung Jo (Korea Institute of Nuclear Safety)
Park, Jeong Soon (Korea Institute of Nuclear Safety)
Oh, Young Jin (KEPCO E&C, Co.)
Publication Information
Transactions of the Korean Society of Mechanical Engineers A / v.37, no.9, 2013 , pp. 1127-1132 More about this Journal
Abstract
The failure of reactor internals may have a significant effect on the safe operation and shutdown of a reactor. Various agings related to neutron irradiation occur or can potentially occur in the reactor internals owing to high neutron irradiation levels. Austenitic stainless steel, one of the principal materials constituting the reactor internals, shows different mechanical material behaviors such as tensile/creep properties and fracture toughness with neutron irradiation levels. This variation should be considered when the structural integrity of the reactor internals against agings during the design lifetime or continued operation period is evaluated. In this study, user subroutine programs considering the variation of mechanical material behaviors with neutron irradiation levels were developed. The programs were validated by testing them for various conditions.
Keywords
Neutron Irradiation; Austenitic Stainless Steel; User Subroutine Program; Reactor Internals; Finite Element Analysis;
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