Fast reactors used lead-bismuth eutectic (LBE) and lead as coolants possess very high level of inherent self-protection and passive safety against severe accident. So, population radiophobia can be overcome. That type...Fast reactors used lead-bismuth eutectic (LBE) and lead as coolants possess very high level of inherent self-protection and passive safety against severe accident. So, population radiophobia can be overcome. That type of reactors can be simultaneously more safely and more cheaply. As all other coolants, LBE and lead coolant (LC) possess the certain virtues and shortcomings. The presented report includes the comparative analysis of characteristic properties of those coolants, their impact on reactor safety, reliability and operating characteristics. The conclusion is made about promising usage of FRs with these coolants in future NP after the experience in operating of the prototypes of such reactors has been obtained.展开更多
The process of heat transfer in a HLMC cross-flow around heat-transfer tubes is not yet thoroughly studied. Therefore, it is of great interest to carry out experimental studies for determining the heat transfer charac...The process of heat transfer in a HLMC cross-flow around heat-transfer tubes is not yet thoroughly studied. Therefore, it is of great interest to carry out experimental studies for determining the heat transfer characteristics in a lead coolant cross-flow around tubes. It is also interesting to explore the velocity and temperature fields in a HLMC flow. To achieve this goal, experts of the NNSTU performed the work aimed at the experimental determination of the temperature and velocity fields in high-temperature lead coolant cross-flows around a tube bundle. The experimental studies were carried out in a specially designed high-temperature liquid-metal facility. The experimental facility is a combination of two high-temperature liquid-metal setups, i.e., FT-2 with a lead coolant and FT-1 with a lead-bismuth coolant, united by an experimental site. The experimental site is a model of the steam generator of the BREST-300 reactor facility. The heat-transfer surface is an in-line tube bank of a diameter of 17 × 3.5 mm, which is made of 10H9NSMFB ferritic-martensitic steel. The temperature of the heat-transfer surface is measured with thermocouples of a diameter of 1 mm being installed in the walls of heat-transfer tubes. The velocity and temperature fields in a high-temperature HLMC flow are measured with special sensors installed in the flow cross section between the rows of heat-transfer tubes. The characteristics of heat transfer and velocity fields in a lead coolant flow were studied in different directions of the coolant flow: The vertical (“top-down” and “bottom-up”) and the horizontal ones. The studies were conducted under the following operating conditions: The temperature of lead was t = 450°C - 5000°C, the thermodynamic activity of oxygen was a = 10-5 - 100, and the lead flow through the experimental site was Q = 3 - 6 m3/h, which corresponds to coolant velocities of V = 0.4 - 0.8 m/s. Comprehensive experimental studies of the characteristics of heat transfer in a lead coolant cross-flow around tubes have been carried out for the first time and the dependences for a controlled and regulated content of the thermodynamically active oxygen impurity and sediments of impurities have been obtained. The effect of the oxygen impurity content in the coolant and characteristics of protective oxide coatings on the temperature and velocity fields in a lead coolant flow is revealed. This is because the presence of oxygen in the coolant and oxide coatings on the surface, which restrict the liquid-metal flow, leads to a change in the characteristics of the wall-adjacent region. The obtained experimental data on the distribution of the velocity and temperature fields in a HLMC flow permit studying the heat-transfer processes and, on this basis, creating program codes for engineering calculations of HLMC flows around heat-transfer surfaces.展开更多
随着中国能源结构深化改革的推进,积极发展核能已成为主要趋势。第四代核能系统代表着核电发展的趋势和技术前沿,因此铅冷快中子反应堆的研究在国际上备受关注。基于麻省理工学院(Massachusetts Institute of Technology,MIT)开发的反...随着中国能源结构深化改革的推进,积极发展核能已成为主要趋势。第四代核能系统代表着核电发展的趋势和技术前沿,因此铅冷快中子反应堆的研究在国际上备受关注。基于麻省理工学院(Massachusetts Institute of Technology,MIT)开发的反应堆蒙特卡洛中子输运方程开源软件OpenMC,以铅冷快中子欧洲示范堆(advanced lead fast reactor European demonstrator,ALFRED)为研究对象,选取两种不同的堆芯冷却剂开展铅冷快堆堆芯物理计算。结果表明:在装载相同燃料的情况下,采用铅-铋冷却剂可以提高堆芯的初始反应性271×10-5;堆芯在正常商运状态下具有更高的堆芯有效缓发中子份额;堆芯的中子能谱更宽、更硬;对于燃料中的239 Pu核素,燃烧效果更好。因此,ALFRED堆芯采用铅-铋合金冷却剂时,具有更高的有效增殖因子,有望提高堆芯的控制性和燃耗性能,并有效减少放射性废物的产生。研究成果为铅冷快中子反应堆欧洲示范堆堆芯设计和性能优化提供了有益的参考。展开更多
New design solutions have been proposed for a BRS-GPG type reactor circuit, which are different from transport and stationary low and medium-powered reactor installations cooled with heavy liquid-metal coolants, and w...New design solutions have been proposed for a BRS-GPG type reactor circuit, which are different from transport and stationary low and medium-powered reactor installations cooled with heavy liquid-metal coolants, and which correspond to the evolutionary development of such installations. While developing these solutions, the available experience in creating and operating So</span><span>viet pilot and commercial power plants cooled with lead-bismuth coolants</span><span> was used, including investigations, primarily experimental ones, carried out by team of authors in justification of a capacity range (50</span></span><span> </span><span>-</span><span> </span><span>250 MW) of low and medium-powered reactor plants with horizontal steam generators (BRS-</span><span> </span><span>GPG) proposed and elaborated at the NNSTU.展开更多
国际原子能机构(International Atomic Energy Agency,IAEA)认为小型模块化反应堆具有很好提高核能安全性、经济性和防止核扩散的能力,是未来核能最具发展前景的堆型之一。为适应未来核能发展的需求,提出了一种铅铋冷却氮化物燃料小型...国际原子能机构(International Atomic Energy Agency,IAEA)认为小型模块化反应堆具有很好提高核能安全性、经济性和防止核扩散的能力,是未来核能最具发展前景的堆型之一。为适应未来核能发展的需求,提出了一种铅铋冷却氮化物燃料小型模块化反应堆(Small Modular Pb-Bi Cooled Reactor with Nitride Nuclear Fuel,SMPBN)设计方案,并利用PIJ组件计算程序和CITATION堆芯计算程序对SMPBN的物理特性和安全特性,包括反应性系数及其随燃耗变化、卸料燃耗、功率峰因子、燃料转换比和停堆余量等进行了深入分析。通过分析,认为SMPBN在20年寿期内,具有很好的燃料转换能力,不需要换料,反应性波动很小,反应性系数均为负值,具有固有安全性,符合国际上第四代反应堆的要求。展开更多
文摘Fast reactors used lead-bismuth eutectic (LBE) and lead as coolants possess very high level of inherent self-protection and passive safety against severe accident. So, population radiophobia can be overcome. That type of reactors can be simultaneously more safely and more cheaply. As all other coolants, LBE and lead coolant (LC) possess the certain virtues and shortcomings. The presented report includes the comparative analysis of characteristic properties of those coolants, their impact on reactor safety, reliability and operating characteristics. The conclusion is made about promising usage of FRs with these coolants in future NP after the experience in operating of the prototypes of such reactors has been obtained.
文摘The process of heat transfer in a HLMC cross-flow around heat-transfer tubes is not yet thoroughly studied. Therefore, it is of great interest to carry out experimental studies for determining the heat transfer characteristics in a lead coolant cross-flow around tubes. It is also interesting to explore the velocity and temperature fields in a HLMC flow. To achieve this goal, experts of the NNSTU performed the work aimed at the experimental determination of the temperature and velocity fields in high-temperature lead coolant cross-flows around a tube bundle. The experimental studies were carried out in a specially designed high-temperature liquid-metal facility. The experimental facility is a combination of two high-temperature liquid-metal setups, i.e., FT-2 with a lead coolant and FT-1 with a lead-bismuth coolant, united by an experimental site. The experimental site is a model of the steam generator of the BREST-300 reactor facility. The heat-transfer surface is an in-line tube bank of a diameter of 17 × 3.5 mm, which is made of 10H9NSMFB ferritic-martensitic steel. The temperature of the heat-transfer surface is measured with thermocouples of a diameter of 1 mm being installed in the walls of heat-transfer tubes. The velocity and temperature fields in a high-temperature HLMC flow are measured with special sensors installed in the flow cross section between the rows of heat-transfer tubes. The characteristics of heat transfer and velocity fields in a lead coolant flow were studied in different directions of the coolant flow: The vertical (“top-down” and “bottom-up”) and the horizontal ones. The studies were conducted under the following operating conditions: The temperature of lead was t = 450°C - 5000°C, the thermodynamic activity of oxygen was a = 10-5 - 100, and the lead flow through the experimental site was Q = 3 - 6 m3/h, which corresponds to coolant velocities of V = 0.4 - 0.8 m/s. Comprehensive experimental studies of the characteristics of heat transfer in a lead coolant cross-flow around tubes have been carried out for the first time and the dependences for a controlled and regulated content of the thermodynamically active oxygen impurity and sediments of impurities have been obtained. The effect of the oxygen impurity content in the coolant and characteristics of protective oxide coatings on the temperature and velocity fields in a lead coolant flow is revealed. This is because the presence of oxygen in the coolant and oxide coatings on the surface, which restrict the liquid-metal flow, leads to a change in the characteristics of the wall-adjacent region. The obtained experimental data on the distribution of the velocity and temperature fields in a HLMC flow permit studying the heat-transfer processes and, on this basis, creating program codes for engineering calculations of HLMC flows around heat-transfer surfaces.
文摘随着中国能源结构深化改革的推进,积极发展核能已成为主要趋势。第四代核能系统代表着核电发展的趋势和技术前沿,因此铅冷快中子反应堆的研究在国际上备受关注。基于麻省理工学院(Massachusetts Institute of Technology,MIT)开发的反应堆蒙特卡洛中子输运方程开源软件OpenMC,以铅冷快中子欧洲示范堆(advanced lead fast reactor European demonstrator,ALFRED)为研究对象,选取两种不同的堆芯冷却剂开展铅冷快堆堆芯物理计算。结果表明:在装载相同燃料的情况下,采用铅-铋冷却剂可以提高堆芯的初始反应性271×10-5;堆芯在正常商运状态下具有更高的堆芯有效缓发中子份额;堆芯的中子能谱更宽、更硬;对于燃料中的239 Pu核素,燃烧效果更好。因此,ALFRED堆芯采用铅-铋合金冷却剂时,具有更高的有效增殖因子,有望提高堆芯的控制性和燃耗性能,并有效减少放射性废物的产生。研究成果为铅冷快中子反应堆欧洲示范堆堆芯设计和性能优化提供了有益的参考。
文摘New design solutions have been proposed for a BRS-GPG type reactor circuit, which are different from transport and stationary low and medium-powered reactor installations cooled with heavy liquid-metal coolants, and which correspond to the evolutionary development of such installations. While developing these solutions, the available experience in creating and operating So</span><span>viet pilot and commercial power plants cooled with lead-bismuth coolants</span><span> was used, including investigations, primarily experimental ones, carried out by team of authors in justification of a capacity range (50</span></span><span> </span><span>-</span><span> </span><span>250 MW) of low and medium-powered reactor plants with horizontal steam generators (BRS-</span><span> </span><span>GPG) proposed and elaborated at the NNSTU.
