通过非设计模式下的控制逻辑系统,提高带有 MED-TVC 海水淡化系统的一体化加压水反应器的运行灵活性

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
A. Naserbegi , M. Aghaie , Kh. Sadeghi , S.H. Ghazaie , E. Sokolova
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引用次数: 0

摘要

在世界许多地区,核电站作为淡水生产的一种能源,发挥着至关重要的作用。核电站可与各种类型的海水淡化厂相结合,生产电力和淡水。本文将被视为最有效的热海水淡化系统的热蒸汽压缩多效海水淡化与加压水反应堆结合起来。热力学建模基于 Thermoflex 软件设计和非设计模式下的能量分析,淡水生产的经济建模则使用 DEEP 软件进行。为了保证淡水生产的灵活性和核电厂的安全性,在设计阶段就采用了具有一定灵活性的适当控制系统,以确保主蒸汽流量的变化能为海水淡化系统提供稳定的能源。通过对蒸汽发生器输出的蒸汽施加 ±30 % 的流量波动,确认了流量控制阀的性能。设计结果表明,以 1.232 美元/立方米的成本每天生产 15,000 立方米的海水淡化量仅会降低基础工厂 0.27% 的净电能效率。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Improving operational flexibility of the integrated pressurized water reactor with the MED-TVC desalination system by control logic systems in the off-design mode
In many regions of the world, nuclear power plants play a vital role as an energy source for freshwater production. They can be coupled with various types of desalination plants to produce electricity and freshwater. In this paper, multi-effect desalination with thermal vapor compression, which is considered the most effective thermal desalination system, has been coupled with a pressurized water reactor. Thermodynamic modeling has been implemented based on energy analysis in the design and off-design modes of Thermoflex software, while economic modeling for freshwater production is conducted using DEEP software. To provide flexibility in freshwater production along with nuclear plant safety, appropriate control systems are incorporated at the design point with a certain degree of flexibility to ensure that variation in the main steam flow rate provides a steady energy source for the desalination system. The performance of the flow control valves was confirmed by applying flow fluctuations of ±30 % to the output steam from the steam generator. The design results showed that producing 15,000 m3/day at a cost of 1.232 $/m3 would reduce only 0.27 % of the net electrical efficiency in the base plant.
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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