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. T...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.展开更多
铅铋共晶(lead-bismutheutectic,LBE)合金具有化学活性低、热特性杰出、耐辐照等优异特性,在核领域具有广泛的应用前景,是第4代核能系统铅冷快堆(lead-cooled fast reactor,LFR)冷却剂的首选材料。然而,高温、高流速、高密度的液态LBE...铅铋共晶(lead-bismutheutectic,LBE)合金具有化学活性低、热特性杰出、耐辐照等优异特性,在核领域具有广泛的应用前景,是第4代核能系统铅冷快堆(lead-cooled fast reactor,LFR)冷却剂的首选材料。然而,高温、高流速、高密度的液态LBE会对核电材料造成严重腐蚀,威胁其服役安全。因此,全面认识与分析应用LBE所面临的挑战,对于解决LBE与结构材料相容性的关键科学和实际工程问题,以及核能的可持续发展具有重要意义。简介了LBE冷却剂的特点,系统地论述了近年来关于LBE腐蚀机理、影响因素的研究现状,针对目前的控制溶解氧气浓度、结构材料设计和腐蚀防护涂层这3种主要解决方案的基本原理、防护机制及国内外最新研究进展进行了较为全面地分析。最后,总结了目前研究中存在的主要问题与不足,并展望了未来发展前景。展开更多
文摘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.
文摘铅铋共晶(lead-bismutheutectic,LBE)合金具有化学活性低、热特性杰出、耐辐照等优异特性,在核领域具有广泛的应用前景,是第4代核能系统铅冷快堆(lead-cooled fast reactor,LFR)冷却剂的首选材料。然而,高温、高流速、高密度的液态LBE会对核电材料造成严重腐蚀,威胁其服役安全。因此,全面认识与分析应用LBE所面临的挑战,对于解决LBE与结构材料相容性的关键科学和实际工程问题,以及核能的可持续发展具有重要意义。简介了LBE冷却剂的特点,系统地论述了近年来关于LBE腐蚀机理、影响因素的研究现状,针对目前的控制溶解氧气浓度、结构材料设计和腐蚀防护涂层这3种主要解决方案的基本原理、防护机制及国内外最新研究进展进行了较为全面地分析。最后,总结了目前研究中存在的主要问题与不足,并展望了未来发展前景。
