2019
DOI: 10.1016/j.net.2019.05.017
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Evaluation of thermal embrittlement in 2507 super duplex stainless steel using thermoelectric power

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Cited by 20 publications
(1 citation statement)
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“…This kind of stainless steel undergoes thermal aging embrittlement during long-term service in reactors (~288-327 • C,~16 MPa), resulting in deficient impact toughness and poor corrosion resistance [13][14][15]. The main problem is that the cast austenitic stainless steel parts in the main coolant pipeline of the primary circuit are pressurized; thus, it is difficult to detect their mechanical properties directly [16][17][18][19]. Therefore, the prediction model and evaluation procedure of thermal aging embrittlement behavior are especially important for in-service inspections, safety assessments and life extension activities of nuclear power plants.…”
Section: Introductionmentioning
confidence: 99%
“…This kind of stainless steel undergoes thermal aging embrittlement during long-term service in reactors (~288-327 • C,~16 MPa), resulting in deficient impact toughness and poor corrosion resistance [13][14][15]. The main problem is that the cast austenitic stainless steel parts in the main coolant pipeline of the primary circuit are pressurized; thus, it is difficult to detect their mechanical properties directly [16][17][18][19]. Therefore, the prediction model and evaluation procedure of thermal aging embrittlement behavior are especially important for in-service inspections, safety assessments and life extension activities of nuclear power plants.…”
Section: Introductionmentioning
confidence: 99%