首页> 外文会议>International conference on nuclear engineering >ANALYSIS OF THERMOPHYSICAL PROPERTIES FOR SELECTED SUPERCRITICAL FLUIDS
【24h】

ANALYSIS OF THERMOPHYSICAL PROPERTIES FOR SELECTED SUPERCRITICAL FLUIDS

机译:选定超临界流体的热物理性质分析

获取原文

摘要

Currently, there are six Generation Ⅳ reactor systems under development worldwide: 1) Very-High-Temperature Reactor (VHTR); 2) Sodium-cooled Fast Reactor (SFR); 3) Supercritical Water-cooled Reactor (SCWR), 4) Gas-cooled Fast Reactor (GFR), 5) Lead-cooled Fast Reactor (LFR); and 6) Molten Salt Reactor (MSR). Of these six systems, Canada has decided to pursue the SCWR as its choice for a Generation Ⅳ reactor, with some research being conducted on the VHTR. One main objective of SCWRs is to increase the thermal efficiency of current nuclear power plants from the 30-35% range to approximately 45-50%. In order to accomplish this, SCWRs are being designed to operate well above the critical point of water at pressures of 25 MPa and reactor outlet temperatures up to 625°C. These operating conditions also make the SCWR, along with the VHTR and other Generation Ⅳ systems, suitable candidates to support thermochemical hydrogen co-generation. The design and operation of a facility capable of accurately and safely conducting experiments in supercritical water is a very expensive task. In order to facilitate our understanding of supercritical heat-transfer phenomena, modeling fluids such as carbon dioxide, refrigerants, ammonia and helium can be used to complement our knowledge of supercritical fluids. Some of these fluids, namely helium and carbon dioxide, have also been considered as potential working fluids in some special designs of reactors and power cycles. The objective of this paper is to investigate the feasibility of using alternative working fluids such as helium and Refrigerant-134a (R-134a) by comparing the fluid and transport properties with those of water. Operating conditions of SCWRs are scaled into those of the modeling fluid, R-134a, in order to provide proper SCWR-equivalent conditions. The equivalent properties for helium, which is one possible coolant for the VHTR, are also discussed. The thermophysical properties for selected working fluids are obtained from NIST REFPROP software. The results indicate that the thermophysical properties of the fluids undergo significant changes within the critical and pseudocritical regions similar to that of supercritical water. A sensitivity analysis for the effect of temperature on selected thermophysical properties at various supercritical pressures was performed.
机译:目前,全世界有六种第四代反应堆系统正在开发中:1)超高温反应堆(VHTR); 2)超高温反应堆(VHTR)。 2)钠冷快堆(SFR); 3)超临界水冷堆(SCWR),4)气冷快堆(GFR),5)铅冷快堆(LFR); 6)熔融盐反应器(MSR)。在这六个系统中,加拿大已决定将SCWR作为Ⅳ代反应堆的选择,并对VHTR进行了一些研究。 SCWR的一个主要目标是将当前核电厂的热效率从30-35%提高到大约45-50%。为了实现这一目标,SCWR设计用于在25 MPa的压力和高达625°C的反应堆出口温度下,在高于水的临界点的条件下运行。这些操作条件也使SCWR以及VHTR和其他Ⅳ代系统成为支持热化学氢联产的合适候选者。能够在超临界水中准确安全地进行实验的设施的设计和操作是一项非常昂贵的任务。为了促进我们对超临界传热现象的理解,可以使用诸如二氧化碳,制冷剂,氨和氦之类的建模流体来补充我们对超临界流体的认识。在反应堆和动力循环的某些特殊设计中,其中的某些流体(即氦气和二氧化碳)也被认为是潜在的工作流体。本文的目的是通过比较流体和水的传输性能,研究使用替代性工作流体(例如氦气和制冷剂134a(R-134a))的可行性。为了提供适当的SCWR等效条件,SCWR的运行条件按比例缩放到建模流体R-134a的运行条件。还讨论了氦的等效特性,氦是VHTR的一种可能的冷却剂。所选工作流体的热物理性质可从NIST REFPROP软件获得。结果表明,流体的热物理性质在临界和伪临界区域内经历了与超临界水相似的显着变化。对温度在各种超临界压力下对所选热物理性质的影响进行了敏感性分析。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号