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Corium melt researches at VESTA test facility

机译:VESTA测试设备中的皮质熔体研究

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VESTA (Verification of Ex-vessel corium STAbilization) and VESTA-S (-small) test facilities were constructed at the Korea Atomic Energy Research Institute in 2010 to perform various corium melt experiments. Since then, several tests have been performed for the verification of an ex-vessel core catcher design for the EU-APR1400. Ablation tests of an impinging ZrO 2 melt jet on a sacrificial material were performed to investigate the ablation characteristics. ZrO 2 melt in an amount of 65–70?kg was discharged onto a sacrificial material through a well-designed nozzle, after which the ablation depths were measured. Interaction tests between the metallic melt and sacrificial material were performed to investigate the interaction kinetics of the sacrificial material. Two types of melt were used: one is a metallic corium melt with Fe 46%, U 31%, Zr 16%, and Cr 7% (maximum possible content of U and Zr for C-40), and the other is a stainless steel (SUS304) melt. Metallic melt in an amount of 1.5–2.0?kg was delivered onto the sacrificial material, and the ablation depths were measured. Penetration tube failure tests were performed for an APR1400 equipped with 61 in-core instrumentation penetration nozzles and extended tubes at the reactor lower vessel. ZrO 2 melt was generated in a melting crucible and delivered down into an interaction crucible where the test specimen is installed. To evaluate the tube ejection mechanism, temperature distributions of the reactor bottom head and in-core instrumentation penetration were measured by a series of thermocouples embedded along the specimen. In addition, lower vessel failure tests for the Fukushima Daiichi nuclear power plant are being performed. As a first step, the configuration of the molten core in the plant was investigated by a melting and solidification experiment. Approximately 5?kg of a mixture, whose composition in terms of weight is UO 2 60%, Zr 10%, ZrO 2 15%, SUS304 14%, and B 4 C 1%, was melted in a cold crucible using an induction heating technique.
机译:2010年,韩国原子能研究所建造了VESTA(前容器中的COR稳定化验证)和VESTA-S(小型)测试设施,以进行各种皮质熔体实验。从那时起,已经进行了几次测试,以验证EU-APR1400的前容器核心捕集器设计。对牺牲材料上的撞击ZrO 2熔体射流进行了烧蚀测试,以研究其烧蚀特性。通过精心设计的喷嘴将65-70?kg的ZrO 2熔体排放到牺牲材料上,然后测量烧蚀深度。进行了金属熔体和牺牲材料之间的相互作用测试,以研究牺牲材料的相互作用动力学。使用了两种类型的熔体:一种是铁含量为46%,U 31%,Zr 16%和Cr为7%(C-40中的U和Zr的最大可能含量)的金属皮质熔体,另一种是不锈钢。钢(SUS304)熔化。将1.5–2.0?kg的金属熔体输送到牺牲材料上,并测量烧蚀深度。对APR1400进行了穿透管故障测试,该APR1400在反应堆下部容器中装有61个岩心仪器穿透喷嘴和延伸管。 ZrO 2熔体在熔融坩埚中产生,并向下传送到安装了试样的相互作用坩埚中。为了评估试管的喷射机理,通过一系列沿样品嵌入的热电偶来测量反应堆底部头部的温度分布和堆芯内仪器的穿透力。此外,正在对福岛第一核电站进行较低的船舶失灵测试。第一步,通过熔融和凝固实验研究了工厂中熔融核的构型。使用感应加热在冷坩埚中熔融约5?kg混合物,其混合物的重量比为UO 2 60%,Zr 10%,ZrO 2 15%,SUS304 14%和B 4 C 1%。技术。

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