2009
DOI: 10.1016/j.jnucmat.2008.12.116
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Effects of residual stress on irradiation hardening in stainless steels

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Cited by 3 publications
(2 citation statements)
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References 7 publications
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“…Irradiation hardening is observed in all the cases irrespective of final treatment conditions. It is of notice that in ODS steel, irradiation hardening is observed after the irradiation at 470 °C, while in the conventional (non-ODS) steels it was not observed when the irradiation temperature was higher than 420 °C [11][12][13][14][15] because of the mutual annihilation between interstitial type dislocation loops (I-loops) and vacancies decomposed from vacancy clusters.…”
Section: Methodsmentioning
confidence: 99%
“…Irradiation hardening is observed in all the cases irrespective of final treatment conditions. It is of notice that in ODS steel, irradiation hardening is observed after the irradiation at 470 °C, while in the conventional (non-ODS) steels it was not observed when the irradiation temperature was higher than 420 °C [11][12][13][14][15] because of the mutual annihilation between interstitial type dislocation loops (I-loops) and vacancies decomposed from vacancy clusters.…”
Section: Methodsmentioning
confidence: 99%
“…These effects will substantially undermine the safety of the in-pile materials within the dispersion nuclear fuel element. As a result, in order to predict the life time of the dispersion fuel element and implement the optimal design, it is necessary to evaluate and simulate the synergistic effects of irradiation hardening with other irradiation behaviors [15].…”
Section: Introductionmentioning
confidence: 99%