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The design of a functionally graded composite for service in high temperature lead and lead-bismuth cooled nuclear reactors

机译:用于高温铅和铅铋冷核反应堆的功能梯度复合材料的设计

摘要

A material that resists lead-bismuth eutectic (LBE) attack and retains its strength at 700°C would be an enabling technology for LBE-cooled reactors. No single alloy currently exists that can economically meet the required performance criteria of high strength and corrosion resistance. A Functionally Graded Composite (FGC) was created with layers engineered to perform these functions. F91 was chosen as the structural layer of the composite for its strength and radiation resistance. Fe-12Cr- 2Si, an alloy developed from previous work in the Fe-Cr-Si system, was chosen as the corrosion-resistant cladding layer because of its chemical similarity to F91 and its superior corrosion resistance in both oxidizing and reducing environments. Fe-12Cr-2Si experienced minimal corrosion due to its self-passivation in oxidizing and reducing environments. Extrapolated corrosion rates are below one micron per year at 700°C. Corrosion of F91 was faster, but predictable and manageable. Diffusion studies showed that 17 microns of the cladding layer will be diffusionally diluted during the three year life of fuel cladding. 33 microns must be accounted for during the sixty year life of coolant piping. 5 cm coolant piping and 6.35 mm fuel cladding were produced on a commercial scale by weld-overlaying Fe-12Cr-2Si onto F91 billets and co-extruding them, followed by pilgering. An ASME certified weld was performed followed by the prescribed quench-and-tempering heat treatment for F91. A minimal heat affected zone was observed, demonstrating field weldability. Finally, corrosion tests were performed on the fabricated FGC at 700°C after completely breaching the cladding in a small area to induce galvanic corrosion at the interface. None was observed. This FGC has significant impacts on LBE reactor design. The increases in outlet temperature and coolant velocity allow a large increase in power density, leading to either a smaller core for the same power rating or more power output for the same size core. This FGC represents an enabling technology for LBE cooled fast reactors.
机译:抵抗铅-铋共晶(LBE)侵蚀并在700°C保持强度的材料将成为LBE冷却反应堆的一项使能技术。当前不存在能够经济地满足所需的高强度和耐腐蚀性性能标准的单一合金。创建了功能梯度复合材料(FGC),其中包含设计用于执行这些功能的层。 F91因其强度和抗辐射性而被选作复合材料的结构层。 Fe-12Cr-2Si是先前在Fe-Cr-Si系统中的工作开发的合金,由于其与F91的化学相似性以及在氧化和还原环境下均具有优异的耐腐蚀性,因此被选作耐腐蚀覆层。由于Fe-12Cr-2Si在氧化和还原环境中具有自钝性,因此腐蚀受到的影响最小。外推腐蚀速率在700°C下每年低于1微米。 F91的腐蚀较快,但可预测且可控制。扩散研究表明,在燃料包层的三年寿命中,17微米的包层将被扩散稀释。在冷却剂管道的六十年使用寿命中,必须考虑到33微米。通过将Fe-12Cr-2Si堆焊在F91坯料上并将它们共挤出,然后进行皮毛化,以商业规模生产了5 cm的冷却剂管道和6.35 mm的燃料包壳。进行ASME认证的焊接,然后对F91进行规定的淬火和回火热处理。观察到最小的热影响区,证明了现场可焊性。最后,在小面积上完全破坏覆层以在界面处引起电化腐蚀之后,在700°C下对制成的FGC进行腐蚀测试。没有观察到。这种FGC对LBE反应器的设计有重大影响。出口温度和冷却剂速度的增加使功率密度大大增加,从而导致对于相同额定功率的铁芯更小或对于相同尺寸铁芯的功率输出更多。该FGC代表了LBE冷却快堆的一项使能技术。

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    Short Michael Philip;

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  • 年度 2010
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  • 正文语种 eng
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