OPTIMAL DESIGN OF SUPERCRITICAL CO2 POWER CYCLE FOR HIGH TEMPERATURE GAS-COOLED REACTOR

被引:0
|
作者
Zhou, Yujia [1 ]
Zhang, Yifan [1 ]
Li, Hongzhi [1 ]
Yao, Mingyu [1 ]
机构
[1] Xian Thermal Power Res Inst Co Ltd, Xian, Peoples R China
关键词
Supercritical CO2; high temperature gas-cooled reactor; broad temperature span; optimal design; parametric analysis; PERFORMANCE;
D O I
暂无
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
The supercritical carbon dioxide (sCO(2)) Brayton cycle has been regarded as a promising technique for future energy conversion systems. sCO(2) recompression cycle configuration has been widely studied for nuclear reactors with the temperature difference between the reactor inlet and outlet restricted to 200 degrees C. However, this cycle configuration may be not suitable for high temperature gas-cooled reactors (HTGR) with a temperature difference up to 500 degrees C. Herein, we aim to develop an optimal sCO(2) cycle configuration for HTGR with a broad temperature span, which has both high cycle efficiency and sufficient mechanical security guaranteed by energy cascade utilization. We propose a recompression cycle combined with reheat and expansion technologies, and perform a parameter optimization in Fortran platform. First, the thermodynamic models of the system are established. Then, the parametric analysis is conducted about the effects of split ratio, temperature difference of the heat exchangers, inlet parameters of turbines and compressors, and isentropic efficiencies on the cycle performance. The sCO(2) cycle tailored for HTGR can achieve a cycle efficiency of 44.98%. Our work not only highlights the design criteria of temperature-match between the HTGR and sCO(2) cycle but also guides the numerical assessment of the steady-state performance.
引用
收藏
页数:7
相关论文
共 50 条
  • [31] Analysis of characteristics of different working fluids for gas turbine cycle with high temperature gas-cooled reactor
    Zhang, Jian-Cheng
    Zhang, Hui-Sheng
    Hedongli Gongcheng/Nuclear Power Engineering, 2009, 30 (04): : 37 - 40
  • [32] HIGH-TEMPERATURE GAS-COOLED BREEDER REACTOR (HTBR)
    YELLOWLEES, JM
    KRAHE, A
    OPPENHEIM, C
    VANSTEENBERGHE, T
    VIEIDER, G
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 20 (APR21): : 704 - 707
  • [33] A simulation method for nuclear power plant with high-temperature gas-cooled reactor
    Chen, Yang
    You, Jiang-Hong
    Shao, Zhi-Jiang
    Qian, Ji-Xin
    Shi, Xu-Hua
    Gao Xiao Hua Xue Gong Cheng Xue Bao/Journal of Chemical Engineering of Chinese Universities, 2014, 28 (01): : 110 - 114
  • [34] HIGH TEMPERATURE GAS-COOLED REACTOR STEAM GENERATOR AND CIRCULATOR
    YAMPOLSK.JS
    COMBUSTION, 1969, 41 (02): : 35 - &
  • [35] MODULARIZED HIGH-TEMPERATURE GAS-COOLED REACTOR SYSTEMS
    LANNING, DD
    NUCLEAR TECHNOLOGY, 1989, 88 (02) : 139 - 156
  • [36] COGENERATION APPLICATION OF THE HIGH-TEMPERATURE GAS-COOLED REACTOR
    MEARS, LD
    RUSS, JE
    ELECTRICAL WORLD, 1984, 198 (03): : 73 - 73
  • [37] SCALE capabilities for high temperature gas-cooled reactor analysis
    Bostelmann, Friederike
    Celik, Cihangir
    Williams, Mark L.
    Ellis, Ronald J.
    Ilas, Germina
    Wieselquist, William A.
    ANNALS OF NUCLEAR ENERGY, 2020, 147
  • [38] STATUS OF HIGH-TEMPERATURE GAS-COOLED REACTOR DEVELOPMENT
    JOHNSTON, TA
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1966, 9 (01): : 313 - &
  • [39] MODULAR HIGH-TEMPERATURE GAS-COOLED REACTOR.
    Shepherd, L.R.
    Nuclear Energy, 1988, 27 (01): : 37 - 47
  • [40] THE HIGH-TEMPERATURE GAS-COOLED REACTOR (HTGR) - PREFACE
    BONILLA, CF
    NUCLEAR ENGINEERING AND DESIGN, 1982, 72 (02) : 109 - 109