1999
DOI: 10.1016/s0022-3115(99)00075-6
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Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals

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Cited by 349 publications
(196 citation statements)
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“…In austenitic stainless steels, which are used as core materials for the boiling water reactor (BWR) and pressurized water reactor (PWR), radiation-induced segregation (RIS) near the grain boundaries degrades their mechanical and chemical properties significantly [4][5][6][7]. The gravity of this problem has been considered as irradiation-assisted stress corrosion cracking (IASCC) caused by the RIS because of the depletion of the chromium concentration near the grain boundaries [8][9][10].…”
Section: Introductionmentioning
confidence: 99%
“…In austenitic stainless steels, which are used as core materials for the boiling water reactor (BWR) and pressurized water reactor (PWR), radiation-induced segregation (RIS) near the grain boundaries degrades their mechanical and chemical properties significantly [4][5][6][7]. The gravity of this problem has been considered as irradiation-assisted stress corrosion cracking (IASCC) caused by the RIS because of the depletion of the chromium concentration near the grain boundaries [8][9][10].…”
Section: Introductionmentioning
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%
“…5 shows atomic maps of the elements in the APT specimen. The volume of the needle was measured to be 114×115×205 nm 3 , and about 10 million atoms were collected and reconstructed. Because of the large number of atoms, the enrichment of Ni and depletion of Cr were not evident in Fig.…”
Section: Methodsmentioning
confidence: 99%
“…Neutron irradiation leads to RIS in SS during service-corresponding to the depletion of Cr and the enrichment of Ni, Si, and P at defect sinks. The depletion of Cr might enhance irradiation-assisted stress corrosion cracking of SS, and this might reduce the integrity of nuclear power plants, especially in case of boiling water reactors [2][3]. Thus, numerous studies on RIS in SS and model alloys have been performed over the three last decades [4][5][6][7][8][9][10][11][12][13].…”
Section: Introductionmentioning
confidence: 99%