Mechanical properties and thermal conductivity of (U,Zr)SiO4
Mechanical properties and thermal conductivity of (U,Zr)SiO4
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(U,Zr)SiO4的机械性能和导热系数
DOI:
10.1016/j.jnucmat.2021.153160
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发表时间:
2021
影响因子:
3.1
通讯作者:
Muta Hiroaki
中科院分区:
文献类型:
--
作者:
Ohishi Yuji;Sun Yifan;Ooi Yuu;Muta Hiroaki
During the core meltdown at the Fukushima Daiichi Nuclear Power Plant (1F), molten core materials penetrated the reactor pressure vessel (RPV), and they may have reacted with the concrete at the bottom of the primary containment vessel (PCV). Through this molten core concrete interaction (MCCI), uranium could potentially dissolve into ZrSiO4and form a (U,Zr)SiO4solid solution. For fuel debris retrieval to proceed smoothly, detailed information on the physical properties and critically characteristic of all possible fuel debris, including MCCI products, is necessary. However, no studies have reported on the physical properties of uranium in ZrSiO4because it is difficult to synthesize. In this study, we fabricated dense (U,Zr)SiO4samples through the spark plasma sintering (SPS) of SiO2and (U,Zr)O2and analyzed the solubility of uranium in ZrSiO4. The solubility limit of uranium in ZrSiO4was found to be within 1.6 – 2.6 at%. The mechanical properties of the (U,Zr)SiO4solid solution were calculated using the samples’ sound velocities. To understand the effect zirconium substitution by uranium has on heat transport, the thermal conductivity was calculated using the thermal diffusivity data measured with laser flash. This is the first study on the thermophysical properties of (U,Zr)SiO4, and it provides us with a better understanding of the properties of MCCI products.
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DOI:
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发表时间:
1996
期刊:
影响因子:
--
作者:
P. Tartaj;Carlos J. Serna;J. Moya;J. Requena;Manuel Ocaña;S. Aza;Francisco Guitián
通讯作者:
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作者:
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3.1
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DOI:
--
发表时间:
2018
期刊:
影响因子:
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作者:
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