The supercritical CO_(2)(sCO_(2))power cycle could improve efficiencies for a wide range of thermal power plants.The sCO_(2)turbine generator plays an important role in the sCO_(2)power cycle by directly converting th...The supercritical CO_(2)(sCO_(2))power cycle could improve efficiencies for a wide range of thermal power plants.The sCO_(2)turbine generator plays an important role in the sCO_(2)power cycle by directly converting thermal energy into mechanical work and electric power.The operation of the generator encounters challenges,including high temperature,high pressure,high rotational speed,and other engineering problems,such as leakage.Experimental studies of sCO_(2)turbines are insufficient because of the significant difficulties in turbine manufacturing and system construction.Unlike most experimental investigations that primarily focus on 100 kW‐or MW‐scale power generation systems,we consider,for the first time,a small‐scale power generator using sCO_(2).A partial admission axial turbine was designed and manufactured with a rated rotational speed of 40,000 rpm,and a CO_(2)transcritical power cycle test loop was constructed to validate the performance of our manufactured generator.A resistant gas was proposed in the constructed turbine expander to solve the leakage issue.Both dynamic and steady performances were investigated.The results indicated that a peak electric power of 11.55 kW was achieved at 29,369 rpm.The maximum total efficiency of the turbo‐generator was 58.98%,which was affected by both the turbine rotational speed and pressure ratio,according to the proposed performance map.展开更多
The supercritical CO_(2) Brayton cycle is considered a promising energy conversion system for Generation IV reactors for its simple layout,compact structure,and high cycle efficiency.Mathematical models of four Brayto...The supercritical CO_(2) Brayton cycle is considered a promising energy conversion system for Generation IV reactors for its simple layout,compact structure,and high cycle efficiency.Mathematical models of four Brayton cycle layouts are developed in this study for different reactors to reduce the cost and increase the thermohydraulic performance of nuclear power generation to promote the commercialization of nuclear energy.Parametric analysis,multi-objective optimizations,and four decision-making methods are applied to obtain each Brayton scheme’s optimal thermohydraulic and economic indexes.Results show that for the same design thermal power scale of reactors,the higher the core’s exit temperature,the better the Brayton cycle’s thermo-economic performance.Among the four-cycle layouts,the recompression cycle(RC)has the best overall performance,followed by the simple recuperation cycle(SR)and the intercooling cycle(IC),and the worst is the reheating cycle(RH).However,RH has the lowest total cost of investment(C_(tot))of$1619.85 million,and IC has the lowest levelized cost of energy(LCOE)of 0.012$/(kWh).The nuclear Brayton cycle system’s overall performance has been improved due to optimization.The performance of the molten salt reactor combined with the intercooling cycle(MSR-IC)scheme has the greatest improvement,with the net output power(W_(net)),thermal efficiencyη_(t),and exergy efficiency(η_(e))improved by 8.58%,8.58%,and 11.21%,respectively.The performance of the lead-cooled fast reactor combined with the simple recuperation cycle scheme was optimized to increase C_(tot) by 27.78%.In comparison,the internal rate of return(IRR)increased by only 7.8%,which is not friendly to investors with limited funds.For the nuclear Brayton cycle,the molten salt reactor combined with the recompression cycle scheme should receive priority,and the gas-cooled fast reactor combined with the reheating cycle scheme should be considered carefully.展开更多
针对超临界CO_(2)动力循环高温承压部件与工质相容性问题,研究了T92耐热钢在600和700℃超临界CO_(2)环境下的腐蚀过程动力学及其热力学产物。采用分子动力学计算了CO_(2)在FeCr合金表面的吸附过程,模拟了T92耐热钢在初始氧化阶段原子的...针对超临界CO_(2)动力循环高温承压部件与工质相容性问题,研究了T92耐热钢在600和700℃超临界CO_(2)环境下的腐蚀过程动力学及其热力学产物。采用分子动力学计算了CO_(2)在FeCr合金表面的吸附过程,模拟了T92耐热钢在初始氧化阶段原子的迁移和分布规律,并基于腐蚀热力学原理,分析了氧化层和碳化物的分布规律,最后通过高温腐蚀实验进行了验证。研究结果表明:700℃时,T92耐热钢氧化层厚度约为600℃时的13.5倍,氧化层结构为外侧Fe_(3)O_(4)层、内侧FeCr_(2)O_(4)层,氧化层内部主要为C 23 C 6型碳化物;CO_(2)优先吸附于Cr原子(111)表面,当Cr与CO_(2)发生反应后,部分形成游离态的C沉积于氧化层表面,并以离子的形式向内扩散;腐蚀过程主要由离子扩散控制,扩散速率随着温度的升高而增大。该研究为超临界CO_(2)材料抗腐蚀性能评估提供了一种复合分析方法,也为关键高温承压部件材料的遴选及腐蚀寿命预测提供了数据支撑。展开更多
基金National Science Fund for Excellent Young Scholars,Grant/Award Number:52022066。
文摘The supercritical CO_(2)(sCO_(2))power cycle could improve efficiencies for a wide range of thermal power plants.The sCO_(2)turbine generator plays an important role in the sCO_(2)power cycle by directly converting thermal energy into mechanical work and electric power.The operation of the generator encounters challenges,including high temperature,high pressure,high rotational speed,and other engineering problems,such as leakage.Experimental studies of sCO_(2)turbines are insufficient because of the significant difficulties in turbine manufacturing and system construction.Unlike most experimental investigations that primarily focus on 100 kW‐or MW‐scale power generation systems,we consider,for the first time,a small‐scale power generator using sCO_(2).A partial admission axial turbine was designed and manufactured with a rated rotational speed of 40,000 rpm,and a CO_(2)transcritical power cycle test loop was constructed to validate the performance of our manufactured generator.A resistant gas was proposed in the constructed turbine expander to solve the leakage issue.Both dynamic and steady performances were investigated.The results indicated that a peak electric power of 11.55 kW was achieved at 29,369 rpm.The maximum total efficiency of the turbo‐generator was 58.98%,which was affected by both the turbine rotational speed and pressure ratio,according to the proposed performance map.
基金This work was supported of National Natural Science Foundation of China Fund(No.52306033)State Key Laboratory of Engines Fund(No.SKLE-K2022-07)the Jiangxi Provincial Postgraduate Innovation Special Fund(No.YC2022-s513).
文摘The supercritical CO_(2) Brayton cycle is considered a promising energy conversion system for Generation IV reactors for its simple layout,compact structure,and high cycle efficiency.Mathematical models of four Brayton cycle layouts are developed in this study for different reactors to reduce the cost and increase the thermohydraulic performance of nuclear power generation to promote the commercialization of nuclear energy.Parametric analysis,multi-objective optimizations,and four decision-making methods are applied to obtain each Brayton scheme’s optimal thermohydraulic and economic indexes.Results show that for the same design thermal power scale of reactors,the higher the core’s exit temperature,the better the Brayton cycle’s thermo-economic performance.Among the four-cycle layouts,the recompression cycle(RC)has the best overall performance,followed by the simple recuperation cycle(SR)and the intercooling cycle(IC),and the worst is the reheating cycle(RH).However,RH has the lowest total cost of investment(C_(tot))of$1619.85 million,and IC has the lowest levelized cost of energy(LCOE)of 0.012$/(kWh).The nuclear Brayton cycle system’s overall performance has been improved due to optimization.The performance of the molten salt reactor combined with the intercooling cycle(MSR-IC)scheme has the greatest improvement,with the net output power(W_(net)),thermal efficiencyη_(t),and exergy efficiency(η_(e))improved by 8.58%,8.58%,and 11.21%,respectively.The performance of the lead-cooled fast reactor combined with the simple recuperation cycle scheme was optimized to increase C_(tot) by 27.78%.In comparison,the internal rate of return(IRR)increased by only 7.8%,which is not friendly to investors with limited funds.For the nuclear Brayton cycle,the molten salt reactor combined with the recompression cycle scheme should receive priority,and the gas-cooled fast reactor combined with the reheating cycle scheme should be considered carefully.
文摘【目的】研究镁橄榄石掺加对减轻超临界CO_(2)环境下油井水泥石的腐蚀渗透性能。【方法】以镁橄榄石粉为外掺料配制不同的油井水泥,分析温度为150℃,CO_(2)总压为50 MPa条件下镁橄榄石水泥石的抗压强度,优选出镁橄榄石粉的最佳掺量;利用渗透率、热重分析(thermo gravimetric analysis,TGA)、X射线衍射(X-Ray diffraction,XRD)和扫描电子显微镜(scanning electron microscope,SEM)进行测试,评价镁橄榄石对油井水泥石抗CO_(2)腐蚀性能的影响,分析镁橄榄石对油井水泥石抗CO_(2)腐蚀的作用机制。【结果】镁橄榄石粉的掺入不会影响油井水泥的流动度,当镁橄榄石粉的质量分数为2%时,对比腐蚀前油井水泥石的,抗压强度提高35.47%,渗透率降低0.0104 m D;腐蚀28 d后,镁橄榄石水泥石的抗压强度为空白水泥石的193.71%,且仍高于腐蚀前。【结论】镁橄榄石是一种抗CO_(2)腐蚀外加剂,能提升油井水泥的抗CO_(2)腐蚀性能。
文摘针对超临界CO_(2)动力循环高温承压部件与工质相容性问题,研究了T92耐热钢在600和700℃超临界CO_(2)环境下的腐蚀过程动力学及其热力学产物。采用分子动力学计算了CO_(2)在FeCr合金表面的吸附过程,模拟了T92耐热钢在初始氧化阶段原子的迁移和分布规律,并基于腐蚀热力学原理,分析了氧化层和碳化物的分布规律,最后通过高温腐蚀实验进行了验证。研究结果表明:700℃时,T92耐热钢氧化层厚度约为600℃时的13.5倍,氧化层结构为外侧Fe_(3)O_(4)层、内侧FeCr_(2)O_(4)层,氧化层内部主要为C 23 C 6型碳化物;CO_(2)优先吸附于Cr原子(111)表面,当Cr与CO_(2)发生反应后,部分形成游离态的C沉积于氧化层表面,并以离子的形式向内扩散;腐蚀过程主要由离子扩散控制,扩散速率随着温度的升高而增大。该研究为超临界CO_(2)材料抗腐蚀性能评估提供了一种复合分析方法,也为关键高温承压部件材料的遴选及腐蚀寿命预测提供了数据支撑。
