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Development of security and safety fuel for Pu-burner HTGR - Test and characterization for ZrC coating -

机译:Pu燃烧器HTGR安全和安全燃料的开发-ZrC涂层的测试和表征-

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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 (PuO_(2)) 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 PuO_(2)-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.
机译:为了开发燃耗达到约500 GWd / t的非常高燃耗的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燃料使用的涂层燃料颗粒具有由二氧化p(PuO_(2))和氧化钇稳定的氧化锆(YSZ)制成的燃料核作为惰性基质。尤其是,碳化锆(ZrC)涂层是3S-TRISO的关键技术之一,它起着吸氧剂的作用,以减少由于辐照期间的内部压力而引起的燃料故障。 2015财年,日本财政开始了直接在由YSZ制成的替代PuO_(2)-YSZ的假核上进行ZrC涂层的研究。作为日本原子能机构开发的溴化物工艺对YSZ颗粒进行ZrC涂层测试的结果,以0.1千克的颗粒负载重量获得了化学计量的ZrC涂层,其厚度为18-21μm。如对YSZ对ZrC溴化物工艺的化学稳定性的热化学分析所表明的,通过扫描透射电子显微镜(STEM)观察的表征未观察到由ZrC溴化物工艺的原料气体暴露的YSZ的劣化。最后,通过溴化物化学气相沉积工艺证明了YSZ颗粒上化学计量ZrC涂层的可重复性。

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