Evaluation of working fluids in an indirect combined cycle in a very high temperature gas-cooled reactor

被引:1
作者
Oh, Chang H. [1 ]
Barner, Robert [1 ]
Davis, Cliff [1 ]
Sherman, Steven [1 ]
机构
[1] Idaho Natl Lab, Idaho Falls, ID 83415 USA
关键词
very high temperature gas-cooled reactor; indirect combined cycle;
D O I
暂无
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 U.S. Department of Energy and Idaho National Laboratory are developing a very high temperature reactor to serve as a demonstration of state-of-the-art nuclear technology. The purpose of the demonstration is twofold: (a) efficient, low-cost energy generation and (b) hydrogen production. Although a next-generation plant could be developed as a single-purpose facility, early designs are expected to be dual purpose, as assumed here. A dual-purpose design with a combined cycle of a Brayton top cycle and a bottom Rankine cycle was investigated. An intermediate heat transport loop for transporting heat to a hydrogen production plant was used Helium, CO2, and a helium-nitrogen mixture were studied to determine the best working fluid in terms of the cycle efficiency. The relative component sizes were estimated for the different working fluids to provide an indication of the relative capital costs. The relative size of the turbomachinery was, measured by comparing the power input/output of the component. For heat exchangers the volume was computed and compared. Parametric studies away from the baseline values of the cycle were performed to determine the effects of varying conditions in the cycle. This gives some insight into the sensitivity of the cycle to various operating conditions as well as trade-offs between efficiency and component size. Parametric studies were carried out on reactor outlet temperature, mass flow, pressure, and turbine cooling.
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页码:1 / 10
页数:10
相关论文
共 19 条
  • [1] [Anonymous], 2003, INEELEXT0300870REV1
  • [2] Bird R.B., 2006, TRANSPORT PHENOMENA, Vsecond, DOI 10.1002/aic.690070245
  • [3] Cohen H., 1996, Gas turbine theory, Vfourth
  • [4] COPSEY B, 2004, P INT C ADV NUCL POW
  • [5] Davis CB, 2005, THERMAL HYDRAULIC AN
  • [6] Dostal V., 2004, MITANPTR100 MIT
  • [7] *ID NAT ENG ENV LA, 2003, RELAP53D COD MAN, V4
  • [8] *IND TECHN REV GRO, 2004, INEELEXT0401816
  • [9] KAYES WM, 1980, CONVECTIVE HEAT MASS
  • [10] Brayton cycle for high-temperature gas-cooled reactors
    Oh, CH
    Moore, RL
    [J]. NUCLEAR TECHNOLOGY, 2005, 149 (03) : 324 - 336