Gen IV SCWR cladding analysis project: Nickel content in SCWR cladding material
2015 5th International Youth Conference on Energy (IYCE)(2015)
摘要
The greater demands on materials in next generation power reactor concepts require exploration of new alloys. Nickel alloys are known to have superior thermal-hydraulic qualities, but perform poorly under neutron bombardment. Atomic Energy of Canada Ltd. and the University of Saskatchewan Department of Physics and Engineering Physics collaborated on a project to study the effects of nickel content in candidate fuel cladding materials. Simulations of each alloy in the reactor environment were carried out to determine the thermal-hydraulic and neutronic characteristics. As well, samples of the candidate alloys were placed in an AutoClave to determine the corrosion characteristics. From the results of these tests, an alloy containing 9% nickel had the best overall performance, but alloys with nickel content up to 56% were also effective.
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关键词
GEN IV SCWR cladding analysis,nickel content,SCWR cladding material,corrosion characteristics,thermal hydraulic characteristics,neutronic characteristics
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