1994
DOI: 10.1016/0022-3115(94)90360-3
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A review of irradiation assisted stress corrosion cracking

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Cited by 251 publications
(75 citation statements)
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“…3) [8][9][10][11]. These cracks usually attributed to IASCC (Irradiation Assisted Stress Corrosion Cracking), can be seen as a consequence of the evolution of plasticity in these materials loaded in a corrosive medium, together with possible evolutions of grain boundary chemistry (due to RIS-Radiation Induced Segregation) [12]. Since evolutions of the macroscopic properties are related to the microstructure ones, understanding microstructure evolution under irradiation is essential to predict lifetime of internals.…”
Section: State Of the Artmentioning
confidence: 99%
“…3) [8][9][10][11]. These cracks usually attributed to IASCC (Irradiation Assisted Stress Corrosion Cracking), can be seen as a consequence of the evolution of plasticity in these materials loaded in a corrosive medium, together with possible evolutions of grain boundary chemistry (due to RIS-Radiation Induced Segregation) [12]. Since evolutions of the macroscopic properties are related to the microstructure ones, understanding microstructure evolution under irradiation is essential to predict lifetime of internals.…”
Section: State Of the Artmentioning
confidence: 99%
“…Over the past decade, there have been significant advances in the understanding of degradation mechanisms in austenitic stainless steel reactor internals as summarized in several review papers [1,2]. Based substantially on this advance in knowledge, efforts to develop austenitic stainless steel structural materials with enhanced radiation resistance have been undertaken.…”
Section: Introductionmentioning
confidence: 99%
“…[8][9][10][11] Under the bombardment of energetic neutrons, a large number of lattice atoms are unlocked from their original sites, generating vacancies and self-interstitials in crystalline materials. While most of the vacancies and interstitials quickly recombine after an initial collision phase, the remaining point defects evolve subsequently into metastable irradiation defects, giving rise to various irradiation effects, such as hardening, embrittlement, enhanced diffusion and segregation, void swelling, creep, etc.…”
Section: Bwrmentioning
confidence: 99%
“…Chromium depletion at grain boundaries resulting from radiation-induced segregation is a possible mechanism to explain the increased susceptibility to intergranular SCC in SSs. 7,9,10 A highly localized plastic flow caused by small irradiation defects is also considered a critical factor of reduced cracking resistance after irradiation. 11,12 Without doubt, irradiation damage plays a key role in elevating the cracking susceptibility of non-sensitized SSs that would otherwise show excellent SCC performance in high-temperature water.…”
Section: Bwrmentioning
confidence: 99%