Processing and microstructural characterisation of a UO2-based ceramic for disposal studies on spent AGR fuel
Processing and microstructural characterisation of a UO2-based ceramic for disposal studies on spent AGR fuel
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用于废 AGR 燃料处置研究的 UO2 基陶瓷的加工和微观结构表征
DOI:
10.1016/j.jnucmat.2014.09.002
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发表时间:
2015
影响因子:
3.1
通讯作者:
Hiezl Z
中科院分区:
文献类型:
--
作者:
Hiezl Z
Preparation and characterisation of a Simulated Spent Nuclear Fuel (SIMFuel), which replicates the chemical state and microstructure of Spent Nuclear Fuel (SNF) discharged from a UK Advanced Gas-cooled Reactor (AGR) after a cooling time of 100 years is described. Given the relatively small differences in radionuclide inventory expected over longer time periods, the SIMFuel studied in this work is expected to be also representative of spent fuel after significantly longer periods (eg 1000 years). Thirteen stable elements were added to depleted UO 2 and sintered to simulate the composition of fuel pellets after burn-ups of 25 and 43 GWd/tU and, as a reference, pure UO 2 pellets were also investigated. The fission product distribution was calculated using the FISPIN code provided by the UK National Nuclear Laboratory. SIMFuel pellets were up to 92% dense and during the sintering process in H 2 atmosphere Mo–Ru–Rh–Pd metallic precipitates and grey-phase ((Ba, Sr)(Zr, RE) O 3 oxide precipitates) formed within the UO 2 matrix. These secondary phases are present in real PWR and AGR SNF. Metallic precipitates are generally spherical and have submicron particle size (0.8±0.7 μm). Spherical oxide precipitates in SIMFuel measured up to 30 μm in diameter, but no data were available in the public domain to compare this to AGR SNF. The grain size of actual AGR SNF (∼ 3–30 μm) is larger than that measured in AGR SIMFuel (∼ 2–5 μm).
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影响因子:
3.1
作者:
M. Cooper;S. Middleburgh;R. Grimes
通讯作者:
R. Grimes
DOI:
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发表时间:
1992
期刊:
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DOI:
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DOI:
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2011
期刊:
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通讯作者:
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DOI:
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发表时间:
1992
期刊:
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