Study on Fast Reactor and Accelerator Target Using Lead and Lead-Bismuth Coolants
采用铅和铅铋冷却剂的快堆和加速器靶材研究
基本信息
- 批准号:11308017
- 负责人:
- 金额:$ 25.45万
- 依托单位:
- 依托单位国家:日本
- 项目类别:Grant-in-Aid for Scientific Research (A)
- 财政年份:1999
- 资助国家:日本
- 起止时间:1999 至 2001
- 项目状态:已结题
- 来源:
- 关键词:
项目摘要
(1) Burnup and safety analyzes were performed for a long life small safe reactor, and the events of UTOP, ULOF and ULOHS were simulated. The feasibility of CANDLE burnup concept was confirmed for a lead-bismuth cooled reactor with 2 m in radius and 0.5 m in radial reflector thickness.(2) The poisons produced by spallation in the lead-bismuth target of accelerator-driven system and the hazard of the long lived radiological products were evaluated.(3) The behaviors of polonium adsorption and the removal of polonium contamination on quartz glass by baking were investigated experimentally.(4) Lead-Bismuth Technology, Material Corrosion and Control of Oxygen Concentration(i) A lead-bismuth flow loop was designed and fabricated, and operated with the desired performance.(ii) The technique of oxygen concentration control in lead-bismuth by means of injecting argon, hydrogen and steam into lead-bismuth was established.(iii) A solid electrolyte oxygen sensor mounted in the lead-bismuth loop pro … More vided a reasonable electro-motive force corresponding to the oxygen potential given by the injection of argon, hydrogen and steam mixture into lead-bismuth.(iv) As a result of two steel corrosion tests at 550 ℃ and 2 m/s for 1,000 hours in a lead-bismuth flow, the weight losses of the high Cr steels : SUS430, SUS405 and STBA26 were lower than the other steels due to Cr oxide corrosion suppression layer. The weight loss and damage of SUS316 were the largest among the tested steels because of high solubility of Ni into lead-bismuth. In the corrosion test at the oxygen concentration of 3.6x10^<-7> wt. %, erosion damage appeared in the test pieces of low Cr steels : SCM420, F82H, STBA26, HCM12, and 2 l/4Cr-1Mo steel. The penetration of lead and bismuth into SCM420, STBA26, STBA28 and SUS316 and the dissolution of Fe and Cr into adherent lead-bismuth in ODS, F82H, NF616 and HCM12 appeared.(v) The dissolution of steel into lead-bismuth and the penetration of lead and bismuth into the steel were simulated by the molecular dynamics method.(5) Thermal-Hydraulics of Lead-Bismuth(i) The flow characteristics of a natural circulation using a gas lift pump was investigated experimentally.(ii) Natural circulation in lead-bismuth cooled reactor was analytically examined.(iii) An electro-magnetic flow meter with MI cable type electrodes plated with Rh was the best performance.(iv) Mass diffusion between lead-bismuth and different liquid metals were well simulated by the molecular dynamics method. Less
(1)对长寿命小型安全反应堆进行了燃耗和安全性分析,模拟了UTOP、ULOF和ULOHS事件。在半径为2 m、径向反射面厚度为0.5 m的铅铋冷却堆上,验证了CANDLE燃耗概念的可行性。(2)对加速器驱动系统中铅铋靶的散裂产生的毒物及长寿命放射性产物的危害进行了评价。(3)实验研究了石英玻璃对钋的吸附行为及焙烧法去除钋污染的效果。(4)铅铋工艺、材料腐蚀与氧浓度控制(1)设计并制作了铅铋流动回路,并按预期性能运行。(二)建立了通过向铅铋中注入氩气、氢气和蒸汽来控制铅铋中氧浓度的技术。(3)在铅铋回路中安装固体电解质氧传感器,得到了合理的电动势,对应于向铅铋注入氩气、氢气和蒸汽混合物所产生的氧势。(iv)通过两次铅铋流中550℃、2m /s、1000 h的腐蚀试验,发现高铬钢SUS430、SUS405和STBA26由于存在氧化铬缓蚀层,其失重率低于其他钢。由于镍在铅铋中的溶解度高,SUS316的重量损失和损伤最大。在氧浓度为3.6x10^<-7> wt. %的腐蚀试验中,SCM420、F82H、STBA26、HCM12、2l /4Cr-1Mo等低铬钢试件均出现了冲蚀损伤。出现了铅和铋对SCM420、STBA26、STBA28和SUS316的渗透,以及ODS、F82H、NF616和HCM12中Fe和Cr对粘附的铅-铋的溶解。(5)用分子动力学方法模拟了钢在铅铋中的溶解和铅铋在钢中的渗透过程。(1)对气举泵自然循环的流动特性进行了实验研究。㈡对铅铋冷却反应堆的自然循环进行了分析研究。(3)采用MI电缆型电极镀铑的电磁流量计性能最好。(四)用分子动力学方法很好地模拟了铅铋与不同液态金属之间的质量扩散。少
项目成果
期刊论文数量(48)
专著数量(0)
科研奖励数量(0)
会议论文数量(0)
专利数量(0)
H.Sekimoto, K.Ryu, Y.Yoshimura: "CANDLE : The New Bumunp Strategy"Nucl.Sci.Eng.. 139(3). 306-317 (2001)
H.Sekimoto、K.Ryu、Y.Yoshimura:“CANDLE:新的 Bumunp 策略”Nucl.Sci.Eng.. 139(3)。
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M.Saito, V.Artisyuk, A.Stankovskii: "Radiological Hazard of Long-Lived Spallation Products in Accelerator-Driven System"IAEA Workshop on Advanced Nuclear Reactor and Fuel Cycle Concepts, ANL, Nov.28-Dec.1. (2000)
M.Saito、V.Artisyuk、A.Stankovskii:“加速器驱动系统中长寿命散裂产物的放射性危害”国际原子能机构先进核反应堆和燃料循环概念研讨会,ANL,11 月 28 日至 12 月 1 日。
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T.Obara, Y.Fujita, Y., Ando, H.Sekimoto: "Removal of Polonium Contamination on Quartz Glass by Baking"Trans.American Nuclear Society. 85. 49 (2001)
T.Obara, Y.Fujita, Y., Ando, H.Sekimoto:“通过烘烤去除石英玻璃上的钋污染”跨美国核协会。
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V. Toshinsky, H. Sekimoto and G. Toshinsky: "Multiobjective Fuel Management Optimization for Self-Fuel-Providing LMFBR Using Genetic Algorithms"Ann. Nucl. Energy. 26[9]. 783-802 (1999)
V. Toshinsky、H. Sekimoto 和 G. Toshinsky:“使用遗传算法对自供燃料 LMFBR 进行多目标燃料管理优化”Ann。
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Takahashi, M., Igashira, M., Obara, T., Sekimoto, H., Kikuchi, K., Aoto, K., Kitano, T.: "Studies on Materials for Heavy-Liquid-Metal-Cooled Reactors in Japan"Proc. of 10^<th> International Conference on Nuclear Engineering, April 14-18, 2002, Arlington,
Takahashi, M.、Igashira, M.、Obara, T.、Sekimoto, H.、Kikuchi, K.、Aoto, K.、Kitano, T.:“日本重液态金属冷却反应堆材料研究
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