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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems
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Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems

机译：开发用于下一代核系统燃料包壳的添加铝的高Cr ODS钢

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A successful example of high-Cr oxide dispersion strengthened (ODS) steels development is introduced with showing key technologies to overcome the issues to meet material requirements for next generation nuclear systems as well as fusion blanket systems. Corrosion issue requires Cr concentration more than 14 wt.%, but aging embrittlement issue requires it less than 16 wt.%. An addition of 4 wt.%Al is effective to improve corrosion resistance of 16 wt.%Cr-ODS steel in supercritical water (SCW) and lead-bismuth eutectics (LBE), while it is detrimental to high-temperature strength. An addition of small amount of Zr or Hf results in a significant increase in creep strength at 973 K in Al-added ODS steels. Feasibility of high-Cr ODS steel without Al addition is assessed for fusion application in terms of corrosion resistance in SCW.
机译：介绍了高铬氧化物弥散强化（ODS）钢材开发的成功示例，其中展示了克服关键问题的关键技术，以满足下一代核系统和聚变层系统的材料要求。腐蚀问题要求Cr浓度大于14 wt。％，而老化脆化问题要求Cr浓度小于16 wt。％。添加4重量％的Al可有效地改善16重量％的Cr-ODS钢在超临界水（SCW）和铅-铋共晶（LBE）中的耐腐蚀性，同时不利于高温强度。添加少量的Zr或Hf会导致添加Al的ODS钢在973 K时的蠕变强度显着提高。根据SCW的耐蚀性，评估了不添加Al的高Cr ODS钢在熔融应用中的可行性。

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