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Fe-based amorphous coating prepared using high-velocity oxygen fuel and its corrosion behavior in static lead-bismuth eutectic alloy

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International Journal of Minerals,Metallurgy and Materials 2022年第11期29卷 2032-2040页

作者： Xiangyang Peng Yuhai Tang Xiangbin Ding Zhichao Lu Shuo Hou Jianming Zhou Shuyin Han Zhaoping Lü Guangyao Lu Yuan Wu Equipment Research Center China Nuclear Power Technology Research Institute Co.Ltd.Shenzhen 518000China State Key Laboratory for Advanced Metals and Materials University of Science&Technology BeijingBeijing 100083China

The Fe_(949.7)Cr_(18)Mn_(1.9)Mo_(7.4)W_(1.6)B_(15.2)C_(3.8)Si_(2) amorphous coating was deposited on T91 steel substrate by using the high-velocity oxygen fuel(HVOF)spray technique to enhance the corrosion resistance of T91 stainless steel in liquid lead-bismuth eutectic(LBE).The corrosion behavior of the T91 steel and coating exposed to oxygen-saturated LBE at 400℃ for 500 h was *** showed that the T91 substrate was severely corroded and covered by a homogeneously distributed dual-layer oxide on the interface contacted to LBE,consisting of an outer magnetite layer and an inner Fe-Cr spinel ***,the amorphous coating with a high glass transition temperature(Tg=550℃)and crystallization temperature(T_(x)=600℃)exhibited dramatically enhanced thermal stability and corrosion *** visible LBE penetration was observed,although small amounts of Fe_(3)O_(4),Cr_(2)O_(3),and PbO were found on the coating *** addition,the amorphicity and interface bonding of the coating layer remained unchanged after the LBE *** Fe-based amorphous coating can act as a stable barrier layer in liquid LBE and have great application potential for long-term service in LBE-cooled fast reactors.

关键词： Fe-based amorphous coating high-velocity oxygen fuel corrosion behavior lead-bismuth eutectic

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Embrittlement effects on ferritic/martensitic steels by liquid lead-bismuth eutectic

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Journal of Chongqing University 2013年第4期12卷 163-169页

作者：高雯 LONG Bin DAI Yong National Lab of Nuclear Fuel Recycle and Materials Nuclear Institute of China Paul Scherrer Institute

Studies of synergetic irradiation effects and liquid lead-bismuth eutectic(LBE) corrosion/embrittlement effects on ferritic/martensitic(F/M) steels are of great importance for developing high power spallation neutron targets(>1 M W) such as the European Spallation Source(ESS) and Accelerator Driven System(ADS) facilities that can be used for transmuting long-lifetime radioactive wastes. Liquid LBE(45Pb-55Bi,in terms of mass fraction) has been selected as the candidate target material in high power spallation neutron targets due to its favourable thermal,physical & chemical properties,and to its high spallation neutron yield. 9Cr F/M steels such as T91(9Cr1M oVNb,in terms of mass fraction) have been chosen as the structural material for the targets due to their good mechanical properties and good resistance to irradiation induced swelling in fission neutron irradiation environments. For developing high power spallation neutron targets,behaviors of F/M steels in spallation neutron target irradiation environments and LBE corrosion/embrittlement effects have been extensively studied. However,many open questions have not been answered. The aim of this paper is to describe the present research situation on this topic. The obtained experimental data about LBE embrittlement effects on F/M steels is summarized and the influence of different parameters involved is analyzed to understand the influence effect on LBE embrittlement effect of F/M s.

关键词： lead-bismuth eutectic T91 ferritic/martensitic embrittlement

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Americium Transmutation in the SVBR-100 Reactor

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World Journal of Nuclear Science and Technology 2020年第3期10卷 116-128页

作者： A. V. Gulevich V. A. Eliseev O. G. Komlev I. V. Tormyshev G. I. Toshinsky JSC “SSC RF-IPPE” Obninsk Russia JSC “AKME-Engineering” Moscow Russia

One of the postponed problems of nuclear power (NP) is the problem of the management of long-lived radioactive waste (RAW), and, first of all, with minor actinides (MA), of which americium-241 is the most difficult. The aim of this work is to study the efficiency of americium transmutation in a fast reactor with a heavy liquid metal coolant lead-bismuth eutectic alloy. The article presents the results of calculations of the transmutation of americium in the SVBR-100 reactor using standard uranium oxide fuel with the addition of americium-241. The obtained values of the rate of transmutation of americium are compared with similar values for the SVBR-100 reactors on MOX-fuel and in the BN-800 reactor.

关键词： SVBR-100 Fast Reactor Nuclear Power lead-bismuth eutectic Minor Actinides Americium Nuclear Fuel Cycle Neutron Spectrum Core

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