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:IV核电厂简易和中间布雷顿氦循环循环汽轮机循环的非设计点演出分析

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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:核电厂(NPP)的设计点(DP)性能相当简单,建立给定的质量流量,涡轮机压缩机压力比(PR)和反应堆核心出口温度(COT)。植物组件对于该点来说是最佳的,但如果工厂的运行条件因部分负载性能而改变,这不再是这种情况。来自测试或以前的操作经验的数据对于基于特征图确定组件的典型部分负载性能有用。然而,当各个组分在植物中连接时,用于部分负荷性能的操作点的范围严重降低。本研究的主要目的是导出简单循环恢复(SCR)和中间冷却循环(ICR)的偏离设计点(ODP),当考虑到-35至50°C的温度范围,并且750至1000°之间的婴儿床C,使用专为本研究设计的建模和性能仿真工具,其计算了对NPP经济学至关重要的最佳运营平衡ODP。结果表明,恢复器高压(HP)侧和电抗器压力损失改变了实际操作参数(质量流量和压缩机PR)。与ICR(5%)相同的恢复器HP损耗相比,SCR的植物循环效率为1%,1%的压力损失为4%的压力损失。除了预冷却器和恢复器低压(LP)损耗之类的其他参数仍然保持相同的操作入口PRS和质量流速,而不管损耗的大小。在公共领域的缺失的情况下,ODP已经用于生产用于一阶ODP计算的特征趋势图。分析打算帮助发电IV NPPS的循环的发展,特别是气体冷却的快速反应器(GFRS)和非常高的温度反应器(VHTRS),其中氦气是冷却剂。

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