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Thermodynamic Analysis of Power Generation Cycles With High-Temperature Gas-Cooled Nuclear Reactor and Additional Coolant Heating Up to 1600°C

机译:高温气体核反应堆发电循环的热力学分析,额外的冷却剂加热高达1600°C

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摘要

Nuclear energy is one of the possibilities ensuring energy security, environmental protection, and high energy efficiency. Among many newest solutions, special attention is paid to the medium size high-temperature gas-cooled reactors (HTGR) with wide possible applications in electric energy production and district heating systems. Actual progress can be observed in the literature and especially in new projects. The maximum outlet temperature of helium as the reactor cooling gas is about 1000 degrees C which results in the relatively low energy efficiency of the cycle not greater than 40-45% in comparison to 55-60% of modern conventional power plants fueled by natural gas or coal. A significant increase of energy efficiency of HTGR cycles can be achieved with the increase of helium temperature from the nuclear reactor using additional coolant heating even up to 1600 degrees C in heat exchanger/gas burner located before gas turbine. In this paper, new solution with additional coolant heating is presented. Thermodynamic analysis of the proposed solution with a comparison to the classical HTGR cycle will be presented showing a significant increase of energy efficiency up to about 66%.
机译:核能是确保能源安全,环保和高能源效率的可能性之一。在许多最新的解决方案中,特别注意中尺寸的高温气体冷却反应器(HTGR),具有广泛的电能生产和区供热系统。在文献中可以观察到实际进展,特别是在新项目中。作为反应器冷却气体的氦的最大出口温度为约1000℃,导致循环的相对低的能量效率,而不是大于40-45%,与天然气推动的现代传统发电厂的55-60%或煤炭。通过使用额外的冷却剂加热在燃气涡轮机之前的热交换器/燃气燃烧器中,通过从核反应堆的氦温度的增加,可以实现HTGR循环能效的显着增加。本文提出了具有额外冷却剂加热的新溶液。将提出与经典HTGR周期相比的所提出的解决方案的热力学分析显示出高达约66%的能效显着增加。

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