Corrosion Mechanism on Heat Transfer Surface of Pressure Boundary Materials used in Nuclear Environments

机译：核环境中压力边界材料传热表面的腐蚀机理

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The ultra-high burnnp more than 100GWd/t and fast neutron spectrum tailoring are considered to be the most promising technologies applied to the advanced MOX LWRs for minimizing the electrical cost and waste management. The development of new cladding materials with the excellent irradiation properties has been conducted to realize these needs. Comparing with UO_2, to increase the internal pressure by FP gas release is accelerated with the co-production of Xe and He in MOX fuels. New stainless steels with the excellent irradiation properties, creep strength and compatibilities to high temperature water were selected to attain the reliability. The irradiation assisted stress corrosion cracking through the past experience in LWR plants is possible to inhibit by new steel making process. The problems of tritium release and PCMI is possible to inhibit by ductile niobium alloy lining.

机译：超过100GWd / t的超高燃耗和快速中子谱调整被认为是最先进的技术，可应用于先进的MOX LWR，以最大程度地减少电力成本和废物管理。为了实现这些需求，已经进行了具有优异辐射性能的新型覆层材料的开发。与UO_2相比，通过MOX燃料中Xe和He的联产，可通过FP气体释放来提高内部压力。选择具有优异辐照性能，蠕变强度和对高温水的相容性的新型不锈钢来获得可靠性。过去在轻水堆工厂的经验所带来的辐照辅助应力腐蚀开裂有可能被新的炼钢工艺所抑制。延性铌合金衬里可以抑制of的释放和PCMI问题。

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《The 3rd International Symposium on Material Chemistry in Nuclear Environment (Material Chemistry '02 MC'02) Mar 13-15, 2002 Tsukuba》|2002年|p.84-91|共8页
会议地点 Tsukuba(JP);Tsukuba(JP);Tsukuba(JP)
作者
K.Kiuchi; H.Ogawa; I.Ioka; Y.Kuroda; T.Anegawa;
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Japan Atomic Energy Research Institute, Department of Nuclear Energy System 2-4 Shirakata Shirane, Tokai-mura, Ibaraki-ken, 319-1195 Japan;

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原文格式 PDF
正文语种 eng
中图分类原子能技术;
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Corrosion Mechanism on Heat Transfer Surface of Pressure Boundary Materials used in Nuclear Environments

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