Optimization study for thermal efficiency of supercritical water reactor nuclear power plant

被引:35
作者
Su, Yali [1 ]
Chaudri, Khurrum Saleem [1 ]
Tian, Wenxi [1 ]
Su, Guanghui [1 ]
Qiu, Suizheng [1 ]
机构
[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Peoples R China
关键词
SCWR; Thermal efficiency; Supercritical steam turbine;
D O I
10.1016/j.anucene.2013.08.023
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The thermal efficiency of Super Critical Water Reactor (SCWR) nuclear power plant is studied here. It is affected by three feedwater regenerative parameters namely enthalpy rise distribution of heaters, corresponding optimum feedwater temperature and number of regenerative stage. These parameters are interlinked. The steam cycle system of SCWR contains two-stage reheating and eight-stage regenerative system. Average Distribution Method (ADM) is used to study the relationships between these parameters. Different thermal efficiency parameters of the circulating system in SCWR are calculated and optimized. The results can be a good reference for the design of steam circulation system in SCWR design. 280 degrees C will be a proper temperature selected for the core inlet. Based on the investigation of existing supercritical steam turbine technology of the supercritical fossil power plant, some useful suggestions are given for the steam turbine design of SCWR. (C) 2013 Elsevier Ltd. All rights reserved.
引用
收藏
页码:541 / 547
页数:7
相关论文
共 13 条
[1]  
[Anonymous], 2002, A Technology Roadmap for Generation IV Nuclear Energy Systems
[2]  
Brandauer M., 2009, 4 INT S SUP WAT COOL
[3]  
Herbell H., 2009, 4 INT S SUP WAT COOL
[4]   Control of a high temperature Supercritical pressure light water cooled and moderated reactor with water rods [J].
Ishiwatari, Y ;
Oka, Y ;
Koshizuka, S .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2003, 40 (05) :298-306
[5]  
Jacopo Buongiorno, 2004, INT C ADV NUCL POW P, P451
[6]  
Lin W.C., 1985, POWER PLANT HOT QUAN
[7]  
Ma F.L., 1992, THERMAL POWER PLANT
[8]  
Oka Y., 2000, P SCR 2000 TOK, P37
[9]  
Salisbury J.K., 1974, STEAM TURBINE THEIR
[10]  
SCHLAGENHAUFER M, 2009, 4 INT S SUP WAT COOL