Plasma and Fusion Research
Volume 17, 2405054 (2022)
Regular Articles
- School of Fundamental Science and Engineering, Waseda University, 3-4-1 Ohkubo, Shinjuku-ku, Tokyo 169-8555, Japan
- 1)
- National Institute for Fusion Science, 322-6 Oroshi, Toki, Gifu 509-5292, Japan
Abstract
For the purpose of further improving the power generation performance by the supercritical CO2 gas turbine
power generation system, aerodynamic optimum and heat transfer flow analysis were carried out for vertical
single-axial bypass control type supercritical CO2 gas turbine power generation system model in the 0.6 GW
class FFHR-b1 nuclear fusion power reactor model. As a result, the following conclusions were obtained.
(1) Since the outlet temperature of the 5-stage final stage of the improved main compressor as an alternative
to the low/high pressure compressor can be lowered to 318 K compared to the conventional design (outlet
temperature 334 K), there are design cases that do not require an intercooler in the conventional design.
(2) As a result of reviewing the structural design and operating conditions of the turbine, the output increased
by about 1.1%.
(3) Since a compact design with a total length of about 2.2 m is possible in the design of the above CO2
gas turbine power generation system (excluding the generator), the feasibility of designing a vertical single-axial
bypass control type supercritical CO2 gas turbine power generation system is clarified.
From these results, the redesigned vertical uniaxial bypass control type supercritical CO2 gas turbine power
generation system is expected to be a compact and economical power generation system that exceeds the power
generation efficiency of the conventional design model up to about 0.6%.
Keywords
super critical CO2 gas turbine, Force Free Helical Reactor (FFHR), bypass control, axial-flow single-shaft design turbine
Full Text
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