The values of effective breeding coefficient Keff in a reactor core of nuclear power plant are calculated for different values of parameters （core structure, fuel assembly component） by using the Monte Carlo method....The values of effective breeding coefficient Keff in a reactor core of nuclear power plant are calculated for different values of parameters （core structure, fuel assembly component） by using the Monte Carlo method. The obtained values of Keff are compared and analysed, which can provide theoretical basis for reactor design.展开更多
Small long-life transportable high temperature gas-cooled reactors(HTRs) are interesting because they can safely provide electricity or heat in remote areas or to industrial users in developed or developing countries....Small long-life transportable high temperature gas-cooled reactors(HTRs) are interesting because they can safely provide electricity or heat in remote areas or to industrial users in developed or developing countries.This paper presents the neutronic design of the U-Battery,which is a 5 MWth block-type HTR with a fuel lifetime of 5–10 years.Assuming a reactor pressure vessel diameter of less than 3.7 m,some possible reactor core configurations of the 5 MWth U-Battery have been investigated using the TRITON module in SCALE 6.The neutronic analysis shows that Layout 12×2B,a scattering core containing 2 layers of 12 fuel blocks each with 20% enriched235U,reaches a fuel lifetime of 10 effective full power years(EFPYs).When the diameter of the reactor pressure vessel is reduced to 1.8 m,a fuel lifetime of 4 EFPYs will be achieved for the 5 MWth U-Battery with a 25-cm thick graphite side reflector.Layouts 6×3 and 6×4 with a 25-cm thick BeO side reflector achieve a fuel lifetime of 7 and 10 EFPYs,respectively.The comparison of the different core configurations shows that,keeping the number of fuel blocks in the reactor core constant,the annular and scattering core configurations have longer fuel lifetimes and lower fuel cost than the cylindrical ones.Moreover,for the 5 MWth U-Battery,reducing the fuel inventory in the reactor core by decreasing the diameter of fuel kernels and packing fraction of TRISO particles is more effective to lower the fuel cost than decreasing the 235U enrichment.展开更多
Non-oriented silicon steel （35W310） and amorphous ribbon （FeT8 Si9B13 amorphous alloy） reactor U-cores are made by welding and dipping paint curing, respectively. Amorphous U-core used to make reactor cut sharply ...Non-oriented silicon steel （35W310） and amorphous ribbon （FeT8 Si9B13 amorphous alloy） reactor U-cores are made by welding and dipping paint curing, respectively. Amorphous U-core used to make reactor cut sharply ed-dy current loss due to high electrical resistivity characteristic, thickness of thin ribbon and insulation of dipping paint. The amorphous alloy has high and constant magnetic permeability, and is more suitable for reactor design power to filter high order harmonic component. Keeping off high magnetostriction district with magnetic flux density of 50-100 mT can weaken influence on inductance of inductor due to elongation of magnetostriction. Amorphous al-loy has a lower temperature rise using the software Infolytica 7.2 simulation.展开更多
This paper presents a coupled magnetic-circuit method for computing the magnetic force of air-core reactor under short-time current. The current and the magnetic flux density are computed first and then the magnetic f...This paper presents a coupled magnetic-circuit method for computing the magnetic force of air-core reactor under short-time current. The current and the magnetic flux density are computed first and then the magnetic force is obtained. Thus, the dynamic stability performance of air-core reactor can be analyzed at the design stage to reduce experimental cost and shorten the lead-time of product development.展开更多
Based on the method of compound and additional conditions under the conditions of the equal temperature rise and the equal potential drop (P.D.) of resistance, the application of design software of dry-type air-core r...Based on the method of compound and additional conditions under the conditions of the equal temperature rise and the equal potential drop (P.D.) of resistance, the application of design software of dry-type air-core reactor is introduced in this thesis. The analytical methods of the inductance are also given. This approach is proved entirely feasible in theory through the simplification with Bartky transformation, and is able to quickly and accurately calculate reactor inductance. This paper presents the analytical methods of the loss of dry-type air-core reactor as well.展开更多
The purpose of the present study is to develop a methodology to evaluate fuel discharge through the CRGT （control-rod guide tube） during CDAs （core-disruptive accidents） of SFRs （sodium-cooled fast reactors）, si...The purpose of the present study is to develop a methodology to evaluate fuel discharge through the CRGT （control-rod guide tube） during CDAs （core-disruptive accidents） of SFRs （sodium-cooled fast reactors）, since fuel discharge will decrease the core reactivity and CRGTs have a potential to provide an effective discharge path. Fuel discharge contains multi-component fluid dynamics with phase changes, and, in the present study, the SFR safety analysis code SIMMER （Sn, implicit, multifield, multicomponent, Eulerian recriticality） was utilized as a technical basis. First, dominant phenomena affecting fuel discharge through the CRGT are identified based on parametric calculations by the SIMMER code. Next, validations on the code models closely relating to these phenomena were carried out based on experimental data. It was shown that the SIMMER code with some model modifications could reproduce the experimental results appropriately. Through the present study, the evaluation methodology for the molten-fuel discharge through the CRGT was successfully developed.展开更多
Fast reactors based on thorium fuel have enhanced inherent safety. Fluoride salt performs well as a coolant in high-temperature nuclear systems. In this paper,we present a reference core for a large fluoride-salt-cool...Fast reactors based on thorium fuel have enhanced inherent safety. Fluoride salt performs well as a coolant in high-temperature nuclear systems. In this paper,we present a reference core for a large fluoride-salt-cooled solid-fuel fast reactor(LSFR) using thorium–uranium fuel cycle. Neutronics physics of the LSFR reference core is investigated with 2D and 3D in-core fuel management strategy. The design parameters analyzed include the fuel volume fraction, power density level and continuous removal of fission products with 3D fuel shuffling that obtains better equilibrium core performance than 2D shuffling. A self-sustained core is achieved for all cases,and the core of 60% fuel volume fraction at 50 MW/m^3 power density is of the best breeding performance(average breeding ratio 1.134). The LSFR core based on thorium fuel is advantageous in its high discharge burn-up of 20–30% fissions per initial heavy metal atom, small reactivity swing over the whole lifetime(to simplify the reactivity control system), the negative reactivity temperature coefficient(intrinsically safe for all cases) and accepted cladding peak radiation damage. The LSFR reactor is a good alternative option for the deployment of a self-sustained thorium-based nuclear system.展开更多
宽能谱超高通量试验堆(Tsinghua High Flux Reactor,THFR)是一种具备国际先进水平的水冷高通量反应堆,其辐照孔道未扰动的平均热、快中子通量可达2×10^(15)n·cm^(-2)·s^(-1),具有中子通量高、能谱范围宽、辐照能力强、...宽能谱超高通量试验堆(Tsinghua High Flux Reactor,THFR)是一种具备国际先进水平的水冷高通量反应堆,其辐照孔道未扰动的平均热、快中子通量可达2×10^(15)n·cm^(-2)·s^(-1),具有中子通量高、能谱范围宽、辐照能力强、功能用途广等突出特点,综合辐照性能居于国际领先水平,在工业、农业、航天、医疗等领域具有重要应用。本文分析了THFR反应堆及相关系统、辐照应用系统的设计特点,包括采用“池壳式”堆本体结构、“低中子自屏”堆芯设计、弧板型燃料组件、旋转控制鼓、多用途辐照孔道设计、“能动-非能动”相结合安全系统设计等,并对该堆在核燃料和材料辐照考验、放射性同位素辐照生产、中子科学研究等领域的应用前景进行了展望。THFR为服务国家重大战略需求、保障人民生命健康、培育和发展新质生产力提供了有力支撑。展开更多
池式研究型反应堆是全球多用途研究堆中的重点类型,因其在安全特性、多用途性和运行维护等方面的突出表现而备受关注。在池式堆中,热功率为1~10 MW的小型研究堆方案设计最为成熟,应用场景最为广泛。为了探索未来池式研究堆堆芯设计及其...池式研究型反应堆是全球多用途研究堆中的重点类型,因其在安全特性、多用途性和运行维护等方面的突出表现而备受关注。在池式堆中,热功率为1~10 MW的小型研究堆方案设计最为成熟,应用场景最为广泛。为了探索未来池式研究堆堆芯设计及其应用场景的发展趋势,首先,根据全球开展RERTR(Reduced Enrichment Research and Test Reactor)低浓化项目并进行堆芯重新设计的小型池式研究堆不同的堆芯方案进行对比,研究分析未来小型池式研究堆堆芯可采用的燃料类型和组件结构,以及目前全球小型池式研究堆的应用情况。其次,总结了小型池式研究堆在燃料类型和堆芯结构两个方面的发展现状,汇总了研究堆各类中子应用场景的技术指标。最终,通过横向对比探究分析推判:未来小型池式研究堆将采用紧凑型堆芯设计,采用高密度的低浓缩铀燃料,以紧凑可移动式小堆芯为基础,以大水池内中子源应用设施为主要发展方向。展开更多
Riser reactor is a key unit in the Fluid Catalytic Cracking (FCC), and it has important influences on increasing the yield coefficient of gas and oil. In this paper, the behaviors of gas-solid two-phase flow in the tr...Riser reactor is a key unit in the Fluid Catalytic Cracking (FCC), and it has important influences on increasing the yield coefficient of gas and oil. In this paper, the behaviors of gas-solid two-phase flow in the traditional y-type riser reactor are investigated by numerical simulation. The calculated particle concentration distribution is in good agreement with the experimental data, which verified the advanced models and calculating methods. The non-uniform distribution, such as core-annulus flow, may result in the unreasonable matching relationship of catalyst-to-oil ratio. An optimized riser with cuneal internals is proposed and the comparison of two different structures of riser reactor is presented. The comparison results show that the cuneal internals in the riser both can block effectively the slip down of the particles near wall region and weaken core-annulus flow structure due to the redistribution of particles. The results also prove that the particle concentration distribution becomes uniform along the axial and radial direction in the optimized riser by adding cuneal internals, which would be benefits for the catalytic cracking reactions.展开更多
This study aims to thoroughly investigate the axial power peaking factors (PPF) within the low-enriched uranium (LEU) core of the Ghana Research Reactor-1 (GHARR-1). This study uses advanced simulation tools, like the...This study aims to thoroughly investigate the axial power peaking factors (PPF) within the low-enriched uranium (LEU) core of the Ghana Research Reactor-1 (GHARR-1). This study uses advanced simulation tools, like the MCNPX code for analysing neutron behavior and the PARET/ANL code for understanding power variations, to get a clearer picture of the reactor’s performance. The analysis covers the initial six years of GHARR-1’s operation and includes projections for its whole 60-year lifespan. We closely observed the patterns of both the highest and average PPFs at 21 axial nodes, with measurements taken every ten years. The findings of this study reveal important patterns in power distribution within the core, which are essential for improving the safety regulations and fuel management techniques of the reactor. We provide a meticulous approach, extensive data, and an analysis of the findings, highlighting the significance of continuous monitoring and analysis for proactive management of nuclear reactors. The findings of this study not only enhance our comprehension of nuclear reactor safety but also carry significant ramifications for sustainable energy progress in Ghana and the wider global context. Nuclear engineering is essential in tackling global concerns, such as the demand for clean and dependable energy sources. Research on optimising nuclear reactors, particularly in terms of safety and efficiency, is crucial for the ongoing advancement and acceptance of nuclear energy.展开更多
铅基快堆(Lead-based Fast Reactor,LFR)是一种极具发展潜力的第四代核能系统,具有良好的非能动安全性和经济性,但在紧急停堆后上腔室内会出现明显的热分层现象,影响堆芯余热排出,从而引发安全问题。本文通过建立简化的1/6上腔室模型,...铅基快堆(Lead-based Fast Reactor,LFR)是一种极具发展潜力的第四代核能系统,具有良好的非能动安全性和经济性,但在紧急停堆后上腔室内会出现明显的热分层现象,影响堆芯余热排出,从而引发安全问题。本文通过建立简化的1/6上腔室模型,采用计算流体力学软件STAR-CCM+开展LFR停堆后上腔室内热分层过程的大涡模拟(Large Eddy Simulation,LES)研究,并基于相关实验数据验证了模型计算的准确性。模拟结果表明,在正常运行工况下,内筒小孔不足以影响上腔室内铅铋共晶合金(Lead-Bismuth Eutectic,LBE)流动;停堆后120 s左右热分层界面形成,400 s左右热分层界面升至内筒顶部,且内筒小孔可显著减缓热分层界面的上升速率。研究成果表明,热分层界面处存在大的温度梯度和不规则涡流,停堆后上腔室内热分层的动态演化及界面特性研究具有重要意义。展开更多
基金Project supported by the National Natural Science Foundation of China(Grant No10647109)
文摘The values of effective breeding coefficient Keff in a reactor core of nuclear power plant are calculated for different values of parameters （core structure, fuel assembly component） by using the Monte Carlo method. The obtained values of Keff are compared and analysed, which can provide theoretical basis for reactor design.
文摘Small long-life transportable high temperature gas-cooled reactors(HTRs) are interesting because they can safely provide electricity or heat in remote areas or to industrial users in developed or developing countries.This paper presents the neutronic design of the U-Battery,which is a 5 MWth block-type HTR with a fuel lifetime of 5–10 years.Assuming a reactor pressure vessel diameter of less than 3.7 m,some possible reactor core configurations of the 5 MWth U-Battery have been investigated using the TRITON module in SCALE 6.The neutronic analysis shows that Layout 12×2B,a scattering core containing 2 layers of 12 fuel blocks each with 20% enriched235U,reaches a fuel lifetime of 10 effective full power years(EFPYs).When the diameter of the reactor pressure vessel is reduced to 1.8 m,a fuel lifetime of 4 EFPYs will be achieved for the 5 MWth U-Battery with a 25-cm thick graphite side reflector.Layouts 6×3 and 6×4 with a 25-cm thick BeO side reflector achieve a fuel lifetime of 7 and 10 EFPYs,respectively.The comparison of the different core configurations shows that,keeping the number of fuel blocks in the reactor core constant,the annular and scattering core configurations have longer fuel lifetimes and lower fuel cost than the cylindrical ones.Moreover,for the 5 MWth U-Battery,reducing the fuel inventory in the reactor core by decreasing the diameter of fuel kernels and packing fraction of TRISO particles is more effective to lower the fuel cost than decreasing the 235U enrichment.
基金Item Sponsored by National High-Tech Research and Development Program (863 Program) of China (2009AA03Z214)
文摘Non-oriented silicon steel （35W310） and amorphous ribbon （FeT8 Si9B13 amorphous alloy） reactor U-cores are made by welding and dipping paint curing, respectively. Amorphous U-core used to make reactor cut sharply ed-dy current loss due to high electrical resistivity characteristic, thickness of thin ribbon and insulation of dipping paint. The amorphous alloy has high and constant magnetic permeability, and is more suitable for reactor design power to filter high order harmonic component. Keeping off high magnetostriction district with magnetic flux density of 50-100 mT can weaken influence on inductance of inductor due to elongation of magnetostriction. Amorphous al-loy has a lower temperature rise using the software Infolytica 7.2 simulation.
基金Supported by Hi-Tech Research and Development Program of China (grants No.2002AA414060)
文摘This paper presents a coupled magnetic-circuit method for computing the magnetic force of air-core reactor under short-time current. The current and the magnetic flux density are computed first and then the magnetic force is obtained. Thus, the dynamic stability performance of air-core reactor can be analyzed at the design stage to reduce experimental cost and shorten the lead-time of product development.
文摘Based on the method of compound and additional conditions under the conditions of the equal temperature rise and the equal potential drop (P.D.) of resistance, the application of design software of dry-type air-core reactor is introduced in this thesis. The analytical methods of the inductance are also given. This approach is proved entirely feasible in theory through the simplification with Bartky transformation, and is able to quickly and accurately calculate reactor inductance. This paper presents the analytical methods of the loss of dry-type air-core reactor as well.
文摘The purpose of the present study is to develop a methodology to evaluate fuel discharge through the CRGT （control-rod guide tube） during CDAs （core-disruptive accidents） of SFRs （sodium-cooled fast reactors）, since fuel discharge will decrease the core reactivity and CRGTs have a potential to provide an effective discharge path. Fuel discharge contains multi-component fluid dynamics with phase changes, and, in the present study, the SFR safety analysis code SIMMER （Sn, implicit, multifield, multicomponent, Eulerian recriticality） was utilized as a technical basis. First, dominant phenomena affecting fuel discharge through the CRGT are identified based on parametric calculations by the SIMMER code. Next, validations on the code models closely relating to these phenomena were carried out based on experimental data. It was shown that the SIMMER code with some model modifications could reproduce the experimental results appropriately. Through the present study, the evaluation methodology for the molten-fuel discharge through the CRGT was successfully developed.
基金supported by the ‘‘Strategic Priority Research Program’’ of the Chinese Academy of Sciences(No.XDA02010200)the Frontier Science Key Program of Chinese Academy of Sciences(No.QYZDY-SSW-JSC016)
文摘Fast reactors based on thorium fuel have enhanced inherent safety. Fluoride salt performs well as a coolant in high-temperature nuclear systems. In this paper,we present a reference core for a large fluoride-salt-cooled solid-fuel fast reactor(LSFR) using thorium–uranium fuel cycle. Neutronics physics of the LSFR reference core is investigated with 2D and 3D in-core fuel management strategy. The design parameters analyzed include the fuel volume fraction, power density level and continuous removal of fission products with 3D fuel shuffling that obtains better equilibrium core performance than 2D shuffling. A self-sustained core is achieved for all cases,and the core of 60% fuel volume fraction at 50 MW/m^3 power density is of the best breeding performance(average breeding ratio 1.134). The LSFR core based on thorium fuel is advantageous in its high discharge burn-up of 20–30% fissions per initial heavy metal atom, small reactivity swing over the whole lifetime(to simplify the reactivity control system), the negative reactivity temperature coefficient(intrinsically safe for all cases) and accepted cladding peak radiation damage. The LSFR reactor is a good alternative option for the deployment of a self-sustained thorium-based nuclear system.
文摘宽能谱超高通量试验堆(Tsinghua High Flux Reactor,THFR)是一种具备国际先进水平的水冷高通量反应堆,其辐照孔道未扰动的平均热、快中子通量可达2×10^(15)n·cm^(-2)·s^(-1),具有中子通量高、能谱范围宽、辐照能力强、功能用途广等突出特点,综合辐照性能居于国际领先水平,在工业、农业、航天、医疗等领域具有重要应用。本文分析了THFR反应堆及相关系统、辐照应用系统的设计特点,包括采用“池壳式”堆本体结构、“低中子自屏”堆芯设计、弧板型燃料组件、旋转控制鼓、多用途辐照孔道设计、“能动-非能动”相结合安全系统设计等,并对该堆在核燃料和材料辐照考验、放射性同位素辐照生产、中子科学研究等领域的应用前景进行了展望。THFR为服务国家重大战略需求、保障人民生命健康、培育和发展新质生产力提供了有力支撑。
文摘池式研究型反应堆是全球多用途研究堆中的重点类型,因其在安全特性、多用途性和运行维护等方面的突出表现而备受关注。在池式堆中,热功率为1~10 MW的小型研究堆方案设计最为成熟,应用场景最为广泛。为了探索未来池式研究堆堆芯设计及其应用场景的发展趋势,首先,根据全球开展RERTR(Reduced Enrichment Research and Test Reactor)低浓化项目并进行堆芯重新设计的小型池式研究堆不同的堆芯方案进行对比,研究分析未来小型池式研究堆堆芯可采用的燃料类型和组件结构,以及目前全球小型池式研究堆的应用情况。其次,总结了小型池式研究堆在燃料类型和堆芯结构两个方面的发展现状,汇总了研究堆各类中子应用场景的技术指标。最终,通过横向对比探究分析推判:未来小型池式研究堆将采用紧凑型堆芯设计,采用高密度的低浓缩铀燃料,以紧凑可移动式小堆芯为基础,以大水池内中子源应用设施为主要发展方向。
文摘Riser reactor is a key unit in the Fluid Catalytic Cracking (FCC), and it has important influences on increasing the yield coefficient of gas and oil. In this paper, the behaviors of gas-solid two-phase flow in the traditional y-type riser reactor are investigated by numerical simulation. The calculated particle concentration distribution is in good agreement with the experimental data, which verified the advanced models and calculating methods. The non-uniform distribution, such as core-annulus flow, may result in the unreasonable matching relationship of catalyst-to-oil ratio. An optimized riser with cuneal internals is proposed and the comparison of two different structures of riser reactor is presented. The comparison results show that the cuneal internals in the riser both can block effectively the slip down of the particles near wall region and weaken core-annulus flow structure due to the redistribution of particles. The results also prove that the particle concentration distribution becomes uniform along the axial and radial direction in the optimized riser by adding cuneal internals, which would be benefits for the catalytic cracking reactions.
文摘This study aims to thoroughly investigate the axial power peaking factors (PPF) within the low-enriched uranium (LEU) core of the Ghana Research Reactor-1 (GHARR-1). This study uses advanced simulation tools, like the MCNPX code for analysing neutron behavior and the PARET/ANL code for understanding power variations, to get a clearer picture of the reactor’s performance. The analysis covers the initial six years of GHARR-1’s operation and includes projections for its whole 60-year lifespan. We closely observed the patterns of both the highest and average PPFs at 21 axial nodes, with measurements taken every ten years. The findings of this study reveal important patterns in power distribution within the core, which are essential for improving the safety regulations and fuel management techniques of the reactor. We provide a meticulous approach, extensive data, and an analysis of the findings, highlighting the significance of continuous monitoring and analysis for proactive management of nuclear reactors. The findings of this study not only enhance our comprehension of nuclear reactor safety but also carry significant ramifications for sustainable energy progress in Ghana and the wider global context. Nuclear engineering is essential in tackling global concerns, such as the demand for clean and dependable energy sources. Research on optimising nuclear reactors, particularly in terms of safety and efficiency, is crucial for the ongoing advancement and acceptance of nuclear energy.
