Study on Fast Reactor and Accelerator Target Using Lead and Lead-Bismuth Coolants
Study on Fast Reactor and Accelerator Target Using Lead and Lead-Bismuth Coolants
批准号:
11308017
负责人:
SEKIMOTO Hiroshi
金额:
$25.45万
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
项目状态:
已结题
起止时间:
1999 至 2001
中文摘要
(1)对长寿命小型安全堆进行了燃耗和安全性分析,模拟了UTOP、ULOF和ULOHS事件。对一个半径为2 m、径向反射层厚度为0.5 m的铅铋冷却堆,证实了CANDLE燃耗概念的可行性。(2)本文对加速器驱动系统铅铋靶中火花产生的毒物及其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石英玻璃上的钋污染。(4)铅铋工艺、材料腐蚀与氧浓度控制(i)设计和制造了铅铋流动回路,并以期望的性能运行。(ii)建立了用氩气、氢气和水蒸气控制铅铋合金中氧浓度的技术。(iii)一种安装在铅铋环管中的固体电解质氧传感器 关于我们 给出了一个合理的电动势对应的氧电位由氩气,氢气和蒸汽混合物注入铅铋。(iv)在550 ℃、2 m/s、1, 000 h铅铋液流中进行了两次钢腐蚀试验,结果表明,高Cr钢SUS 430、SUS 405和STBA 26的腐蚀失重均低于其它钢,这是由于Cr氧化物腐蚀抑制层的存在。由于Ni在铅铋合金中的高溶解度,SUS 316钢的失重和损伤最大。在氧浓度为3.6 × 10 ~(-3)<-7>wt.低Cr钢SCM 420、F82 H、STBA 26、HCM 12和21/4Cr-1 Mo钢试样均出现冲蚀损伤。铅和铋在SCM 420、STBA 26、STBA 28和SUS 316中发生了渗透,而铁和铬在ODS、F82 H、NF 616和HCM 12中发生了溶解。(v)用分子动力学方法模拟了钢在铅铋合金中的溶解过程和铅铋合金在钢中的渗透过程。(5)铅铋矿的热工水力学研究(一)实验研究了采用气举泵的自然循环的流动特性。(ii)对铅铋冷却堆的自然循环进行了分析研究。(iii)具有镀有Rh的MI电缆型电极的电磁流量计的性能最好。(iv)采用分子动力学方法模拟了铅铋合金与不同液态金属之间的质量扩散过程。少
英文摘要
(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
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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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