2016
DOI: 10.1016/j.nimb.2015.12.001
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Surface, structural and tensile properties of proton beam irradiated zirconium

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Cited by 27 publications
(10 citation statements)
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References 30 publications
(42 reference statements)
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“…For site specific applications, conventional mechanical tests with large samples typically incorporate the region of interest with other regions and separating the relevant component from the global response can be difficult. Such approaches become impractical when the region of interest becomes minimal in size relative to the bulk, with the situation complicated further by property gradients and interactions between constituent parts [8]. A more practical option is to reduce the size of the samples so that they only contain the region or regions of interest.…”
Section: Introductionmentioning
confidence: 99%
“…For site specific applications, conventional mechanical tests with large samples typically incorporate the region of interest with other regions and separating the relevant component from the global response can be difficult. Such approaches become impractical when the region of interest becomes minimal in size relative to the bulk, with the situation complicated further by property gradients and interactions between constituent parts [8]. A more practical option is to reduce the size of the samples so that they only contain the region or regions of interest.…”
Section: Introductionmentioning
confidence: 99%
“…The main alloying elements present in zirconium alloys are niobium and tin. Those alloys are used in nuclear power engineering for their advantageous proprieties, such as low effective cross-section for capture of thermal neutrons, good thermal conductivity, high corrosion resistance, satisfactory mechanical properties within temperature range of the cooling medium, and resistance to radiation damage [1][2][3][4][5][6][7][8].…”
Section: Introductionmentioning
confidence: 99%
“…The transmutation reactions (n, α) and (n, p) generate He atoms and H atoms that will degrade service performance with displacement damage including embrittlement, hardening, and irradiation swelling [12]. Therefore, the irradiation behavior of newly developed Zr alloys needs to be investigated before their use in commercial nuclear reactors.…”
Section: Introductionmentioning
confidence: 99%