钚燃烧器HTGR安全与安全燃料的研制

M. Goto
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引用次数: 1

摘要

为了研制达到500gwd /t左右的超高燃耗的pu燃烧器高温气冷堆(HTGR),提出了安全性和安全性燃料(3S-TRISO燃料)。3S-TRISO燃料采用包覆燃料颗粒,燃料核由二氧化钚(PuO2)和钇稳定氧化锆(YSZ)作为惰性基质制成。其中碳化锆(ZrC)涂层是3S-TRISO的关键技术之一,它可以作为吸氧剂,减少辐照过程中由于内压引起的燃料失效。在日本2015财政年度开始了在YSZ代替PuO2-YSZ制成的假核上直接涂覆ZrC涂层的研究。采用日本原子能机构开发的溴化物法对YSZ颗粒进行了ZrC涂层试验,得到了厚度为18 ~ 21 μm、颗粒载荷为0.1 kg的ZrC涂层。通过对YSZ对ZrC溴化过程的化学稳定性进行热化学分析,通过扫描透射电镜(STEM)观察,YSZ在ZrC溴化过程的源气体暴露下未见变质。最后,通过溴化物化学气相沉积工艺,证明了化学计量ZrC涂层在YSZ颗粒上的可重复性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Development of Security and Safety Fuel for Pu-burner HTGR
To develop Pu-burner high temperature gas-cooled reactor (HTGR) attaining very high burn-up around 500 GWd/t, the security and safety fuel (3S-TRISO fuel) is proposed. The 3S-TRISO fuel employs the coated fuel particle with a fuel kernel made of plutonium dioxide (PuO2) and yttria stabilized zirconia (YSZ) as an inert matrix. Especially, a zirconium carbide (ZrC) coating is one of key technologies of the 3S-TRISO, which performs as an oxygen getter to reduce the fuel failure due to internal pressure during the irradiation. R&Ds on ZrC coating directly on the dummy kernel made of YSZ which surrogates PuO2-YSZ have been started in the Japanese fiscal year 2015. As results of ZrC coating tests on YSZ particle by the bromide process developed in Japan Atomic Energy Agency, stoichiometric ZrC coatings with 18 21 μm of thicknesses were obtained with 0.1 kg of particle loading weight. As indicated by a thermochemical analysis on the chemical stability of YSZ against the ZrC bromide process, no deterioration of YSZ exposed by source gases of ZrC bromide process was observed through the characterization by Scanning Transmission Electron Microscope (STEM) observation. Finally, reproducibility of stoichiometric ZrC coating on YSZ particle was demonstrated by the bromide chemical vapor deposition process.
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