首页> 外文会议>International conference on nuclear engineering >ANALYSES OF OFF-DESIGN POINT PERFORMANCES OF SIMPLE AND INTERCOOLED BRAYTON HELIUM RECUPERATED GAS TURBINE CYCLES FOR GENERATION IV NUCLEAR POWER PLANTS
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ANALYSES OF OFF-DESIGN POINT PERFORMANCES OF SIMPLE AND INTERCOOLED BRAYTON HELIUM RECUPERATED GAS TURBINE CYCLES FOR GENERATION IV NUCLEAR POWER PLANTS

机译:发电用IV型核电站简单,中冷布雷顿氦气再生燃气轮机离点性能分析

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The Design Point (DP) performance of a Nuclear Power Plant (NPP) is fairly straightforward to establish for a given mass flow rate, turbomachinery compressor Pressure Ratio (PR) and reactor Core Outlet Temperature (COT). The plant components are optimum for that point but this is no longer the case if the plant's operating conditions are changed for part-load performance. Data from tests or previous operating experiences are useful in determining typical part load performance of components based on characteristic maps. However, when individual components are linked in a plant, the range of operating points for part load performances are severely reduced. The main objective of this study is to derive Off-Design Points (ODPs) for the Simple Cycle Recuperated (SCR) and Intercooled Cycle Recuperated (ICR) when considering a temperature range of -35 to 50°C and COTs between 750 to 1000°C, using a modelling & performance simulation tool designed specifically for this study, which calculates the best operational equilibrium ODPs that are critical to the economics of the NPP. Results show that the recuperator High-Pressure (HP) side and reactor pressure losses alter the actual operating parameters (mass flow rate and compressor PR). The SCR yielded a drop in plant cycle efficiency of 1% for a 4% pressure loss in comparison to the ICR (5%) for the same amount of recuperator HP losses. Other parameters such as the precooler and recuperator Low-Pressure (LP) losses still retain the same operating inlet PRs and mass flow rates regardless of the magnitude of the losses. In the absence of characteristic maps in the public domain, the ODPs have been used to produce characteristic trend maps for first order ODP calculations. The analyses intend to aid the development of cycles for Generation IV NPPs specifically Gas Cooled Fast Reactors (GFRs) and Very High Temperature Reactors (VHTRs), where helium is the coolant.
机译:对于给定的质量流量,涡轮机械压缩机的压力比(PR)和反应堆堆芯出口温度(COT),要确定给定的质量流量,核电厂(NPP)的设计点(DP)性能非常简单。在这一点上,工厂组件是最佳的,但是如果为了部分负载性能而更改工厂的运行条件,则不再是这种情况。来自测试或先前操作经验的数据可用于基于特性图确定组件的典型零件负载性能。但是,当工厂中的各个组件链接在一起时,严重降低了部分负载性能的工作点范围。这项研究的主要目的是在考虑温度范围-35至50°C和COT在750至1000°之间时,得出简单循环回热(SCR)和中冷循环回热(ICR)的非设计点(ODP)。 C,使用专门为此研究设计的建模和性能模拟工具,该工具计算出对NPP的经济性至关重要的最佳运行平衡ODP。结果表明,换热器的高压侧和反应堆压力损失会改变实际的运行参数(质量流量和压缩机PR)。 SCR导致压力损失为4%时工厂循环效率下降了1%,而同量的换热器HP损失则为ICR(5%)。其他参数(例如,预冷器和换热器的低压(LP)损失)仍然保持相同的工作入口PR和质量流率,而不管损失的大小如何。在公共领域中不存在特征图的情况下,ODP已被用于生成用于一阶ODP计算的特征趋势图。这些分析旨在帮助开发第四代核电厂,特别是气冷快堆(GFR)和超高温反应堆(VHTR)的循环,其中氦是冷却剂。

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