The stability of matrix graphite under neutron irradiation and in corrosive environments is crucial for the safe operation of molten salt reactors(MSRs).Raman spectroscopy and a slow positron beam were employed to inv...The stability of matrix graphite under neutron irradiation and in corrosive environments is crucial for the safe operation of molten salt reactors(MSRs).Raman spectroscopy and a slow positron beam were employed to investigate the effects of He ion irradiation fluences and subsequent annealing on the microstructure and defects of the matrix graphite.He ions with 500 keV energy and fluences ranging from 1.1×10^(15)ions∕cm^(2)to 3.5×10^(17)ions∕cm^(2)were used to simulate neutron irradiation at 300 K.The samples with an irradiation fluence of 3.5×10^(16)ions∕cm^(2)were subjected to isochronal annealing at different temperatures(573 K,873 K and 1173 K)for 3 h.The Raman results revealed that the D peak gradually increased,whereas the intrinsic G peak decreased with increasing irradiation fluence.At the same irradiation fluence,the D peak gradually decreased,whereas the intrinsic G peak increased with increasing annealing temperature.Slow positron beam analysis demonstrated that the density or size of irradiation defects(vacancy type)increased with higher irradiation fluence,but decreased rapidly with increasing annealing temperature.The Raman spectral analysis of sample cross sections subjected to high irradiation fluences revealed the emergence of amorphization precisely at the depth where ion damage was most pronounced,whereas the surface retained its crystalline structure.Raman and positron annihilation analyses indicated that the matrix graphite exhibited good irradiation resistance to He ions at 300 K.However,vacancy-type defects induced by He ion irradiation exhibit poor thermal stability and can be easily removed during annealing.展开更多
开发具有优异综合性能的核反应堆结构材料是核能发展的基础,并且是长期以来制约核能推广的难点之一。多主元合金(multiprincipal element alloys,MEAs)因具有良好的抗辐照性能、力学性能而被认为是先进反应堆结构材料的候选材料,为新型...开发具有优异综合性能的核反应堆结构材料是核能发展的基础,并且是长期以来制约核能推广的难点之一。多主元合金(multiprincipal element alloys,MEAs)因具有良好的抗辐照性能、力学性能而被认为是先进反应堆结构材料的候选材料,为新型抗辐照材料的设计开辟了广阔空间。近年来,有关多主元合金在辐照损伤方面的研究多试图揭示多主元合金一些因素和特性对辐照过程中缺陷形成与演变的影响。例如:主元种类和数目、主元浓度、晶格畸变、化学短程序等。尽管现有的一些研究结果表明以上因素可以提高多主元合金抗辐照损伤能力,但是在不同辐照条件下,以上因素对多主元合金中缺陷形成和演变的影响机制存在较大差异,难以得出普适性的结论。本文围绕FCC和BCC系两类多主元合金的辐照肿胀、氦泡形成、辐照诱导元素偏析和相变、辐照硬化四方面内容,综述了近年来多主元合金在辐照损伤方面的研究进展,总结了多主元合金提高抗辐照性能的作用机制,并在此基础上对核电结构用多主元合金的未来研究方向做出了展望,包括短程序调控、高熵陶瓷、增材制造、高通量结合机器学习加速材料开发等。最后指出必须从合金成分设计的角度出发,基于材料服役的实际环境来设计新型抗辐照多主元合金。展开更多
基金supported by the National Natural Science Foundation of China(Nos.12005289,52072397)State Key Laboratory of Nuclear Detection and Electronics,University of Science and Technology of China(SKLPDE-KF-202316).
文摘The stability of matrix graphite under neutron irradiation and in corrosive environments is crucial for the safe operation of molten salt reactors(MSRs).Raman spectroscopy and a slow positron beam were employed to investigate the effects of He ion irradiation fluences and subsequent annealing on the microstructure and defects of the matrix graphite.He ions with 500 keV energy and fluences ranging from 1.1×10^(15)ions∕cm^(2)to 3.5×10^(17)ions∕cm^(2)were used to simulate neutron irradiation at 300 K.The samples with an irradiation fluence of 3.5×10^(16)ions∕cm^(2)were subjected to isochronal annealing at different temperatures(573 K,873 K and 1173 K)for 3 h.The Raman results revealed that the D peak gradually increased,whereas the intrinsic G peak decreased with increasing irradiation fluence.At the same irradiation fluence,the D peak gradually decreased,whereas the intrinsic G peak increased with increasing annealing temperature.Slow positron beam analysis demonstrated that the density or size of irradiation defects(vacancy type)increased with higher irradiation fluence,but decreased rapidly with increasing annealing temperature.The Raman spectral analysis of sample cross sections subjected to high irradiation fluences revealed the emergence of amorphization precisely at the depth where ion damage was most pronounced,whereas the surface retained its crystalline structure.Raman and positron annihilation analyses indicated that the matrix graphite exhibited good irradiation resistance to He ions at 300 K.However,vacancy-type defects induced by He ion irradiation exhibit poor thermal stability and can be easily removed during annealing.
文摘开发具有优异综合性能的核反应堆结构材料是核能发展的基础,并且是长期以来制约核能推广的难点之一。多主元合金(multiprincipal element alloys,MEAs)因具有良好的抗辐照性能、力学性能而被认为是先进反应堆结构材料的候选材料,为新型抗辐照材料的设计开辟了广阔空间。近年来,有关多主元合金在辐照损伤方面的研究多试图揭示多主元合金一些因素和特性对辐照过程中缺陷形成与演变的影响。例如:主元种类和数目、主元浓度、晶格畸变、化学短程序等。尽管现有的一些研究结果表明以上因素可以提高多主元合金抗辐照损伤能力,但是在不同辐照条件下,以上因素对多主元合金中缺陷形成和演变的影响机制存在较大差异,难以得出普适性的结论。本文围绕FCC和BCC系两类多主元合金的辐照肿胀、氦泡形成、辐照诱导元素偏析和相变、辐照硬化四方面内容,综述了近年来多主元合金在辐照损伤方面的研究进展,总结了多主元合金提高抗辐照性能的作用机制,并在此基础上对核电结构用多主元合金的未来研究方向做出了展望,包括短程序调控、高熵陶瓷、增材制造、高通量结合机器学习加速材料开发等。最后指出必须从合金成分设计的角度出发,基于材料服役的实际环境来设计新型抗辐照多主元合金。
