2011
DOI: 10.1016/j.jnucmat.2011.02.024
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Creep behaviour of modified 9Cr–1Mo ferritic steel

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Cited by 115 publications
(52 citation statements)
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“…It can be seen that these values are much higher and do not reflect the true value of the activation energy. Higher apparent creep activation energies for different high strength Cr-Mo steels have also been reported by different studies [39,40].…”
Section: Creep Behaviour Analysissupporting
confidence: 69%
“…It can be seen that these values are much higher and do not reflect the true value of the activation energy. Higher apparent creep activation energies for different high strength Cr-Mo steels have also been reported by different studies [39,40].…”
Section: Creep Behaviour Analysissupporting
confidence: 69%
“…The creep strain in the tertiary creep stage accumulated more rapidly than in the primary and steady-state creep stages, which is a result of necking prior to fracture. The stress dependence of minimum creep rate m  obeyed Norton's power law [9]:…”
Section: Resultsmentioning
confidence: 99%
“…In the second set (Set-2), the creep-rupture data consisted of 1072 data points. In addition to the data in Set-1, a significantly large amount of creep-rupture data was obtained from different sources from Japan [19][20][21], Europe [22][23][24], USA [25][26][27][28], and the Indira Gandhi Centre for Atomic Research (IGCAR), India [4]. The larger creep rupture database for Grade 91 steel was prepared by digitizing the published document data.…”
Section: Two Sets Of Creep Rupture Datamentioning
confidence: 99%
“…The steel developed by the addition of strong carbide/nitride forming elements such as V and Nb along with the controlled addition of N in the plain 9Cr-1Mo steel, offers a good combination of high creep strength and ductility over long exposures at high temperatures [1][2][3][4]. In view of its superior creep strength, Grade 91 steel has been chosen as a candidate structural material for the steam generator, intermediate heat exchangers (IHX), and primary pipes of a generation-IV (Gen-IV) sodium-cooled fast reactor (SFR).…”
Section: Introductionmentioning
confidence: 99%