Abstract
The supercritical CO2 Brayton cycle is considered a promising energy conversion system for Generation IV reactors for its simple layout, compact structure, and high cycle efficiency. Mathematical models of four Brayton cycle layouts are developed in this study for different reactors to reduce the cost and increase the thermohydraulic performance of nuclear power generation to promote the commercialization of nuclear energy. Parametric analysis, multi-objective optimizations, and four decision-making methods are applied to obtain each Brayton scheme’s optimal thermohydraulic and economic indexes. Results show that for the same design thermal power scale of reactors, the higher the core’s exit temperature, the better the Brayton cycle’s thermo-economic performance. Among the four-cycle layouts, the recompression cycle (RC) has the best overall performance, followed by the simple recuperation cycle (SR) and the intercooling cycle (IC), and the worst is the reheating cycle (RH). However, RH has the lowest total cost of investment (Ctot) of $1619.85 million, and IC has the lowest levelized cost of energy (LCOE) of 0.012 $/(kWh). The nuclear Brayton cycle system’s overall performance has been improved due to optimization. The performance of the molten salt reactor combined with the intercooling cycle (MSR-IC) scheme has the greatest improvement, with the net output power (Wnet), thermal efficiency ηt, and exergy efficiency (ηe) improved by 8.58%, 8.58%, and 11.21%, respectively. The performance of the lead-cooled fast reactor combined with the simple recuperation cycle scheme was optimized to increase Ctot by 27.78%. In comparison, the internal rate of return (IRR) increased by only 7.8%, which is not friendly to investors with limited funds. For the nuclear Brayton cycle, the molten salt reactor combined with the recompression cycle scheme should receive priority, and the gas-cooled fast reactor combined with the reheating cycle scheme should be considered carefully.
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Data availability
The data that support the findings of this study are openly available in Science Data Bank at https://cstr.cn/31253.11.sciencedb.13640 and https://www.doi.org/https://doi.org/10.57760/sciencedb.13640.
Abbreviations
- GFR:
-
Gas-cooled fast reactor
- SFR:
-
Sodium-cooled fast reactor
- LFR:
-
Lead-cooled fast reactor
- MSR:
-
Molten salt reactor
- SR:
-
Simple recuperation cycle
- RC:
-
Recompression cycle
- RH:
-
Re-heating cycle
- IC:
-
Intercooling cycle
- SC:
-
Specific cost
- LCOE:
-
Levelized cost of energy
- IRR:
-
Internal rate of return
- PBP:
-
Payback period
- SP:
-
Size parameters
- APR:
-
Area per net output power
- HX:
-
Heat exchanger
- HTR:
-
High-temperature recuperator
- LTR:
-
Low-temperature recuperator
- MC:
-
Main compressor
- DMM:
-
Decision-making method
- NSGA:
-
Non-dominated sorting genetic algorithm
- ORC:
-
Organic Rankine cycle
- PC:
-
Pre-cooler
- RC:
-
Recompressor
- Turb:
-
Turbine
- S-CO2BC:
-
Supercritical carbon dioxide Brayton cycle
- A :
-
Area, m2
- c :
-
Heat capacity, J/K
- C :
-
Cost, $
- CF:
-
Cash flow, $
- d :
-
Flow channel diameter, m
- D :
-
Hydraulic diameter, m
- f :
-
Friction coefficient
- h :
-
Specific enthalpy, kJ/kg
- I :
-
Exergy destruction, W
- L :
-
Channel length, m
- m :
-
Mass flow rate, kg/s
- p :
-
Pitch, mm
- P :
-
Pressure, kPa
- PR:
-
Pressure ratio
- Q :
-
Heat energy, W
- s :
-
Specific entropy, kJ/(kg K)
- t :
-
Thickness, mm
- T :
-
Temperature, K
- V :
-
Volume flow, m2/s
- W :
-
Work, kJ
- 0:
-
Ambient conditions
- cold:
-
Cold fluid
- hot:
-
Hot fluid
- e:
-
Exergy
- f:
-
Work fluid
- net:
-
Net
- i :
-
State point
- in:
-
Inlet
- min:
-
Minimum
- max:
-
Maximum
- out:
-
Outlet
- tot:
-
Total
- rev:
-
Revenues
- xp:
-
Expenses
- c:
-
Compressor
- t:
-
Turbine
- ε :
-
Surface roughness
- η :
-
Efficiency
- μ :
-
Kinematic viscosity
- δ :
-
Relative roughness
- ρ :
-
Density
- α :
-
Heat transfer coefficient
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All authors contributed to the study conception and design. Material preparation, data collection, and analysis were performed by G-PY, Y-FC, NZ, and P-JM. The first draft of the manuscript was written by G-PY and Y-FC and supervised by P-JM, and all authors commented on previous versions of the manuscript. All authors read and approved the final manuscript.
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This work was supported of National Natural Science Foundation of China Fund (No. 52306033), State Key Laboratory of Engines Fund (No. SKLE-K2022-07), and the Jiangxi Provincial Postgraduate Innovation Special Fund (No. YC2022-s513).
Appendix: Nusselt number and friction factor calculation
Appendix: Nusselt number and friction factor calculation
For the semi-circular straight channel PCHE, the Nussle number is calculated by the Gnielinski correlation [44]. The Nussle number in Eq. (13) is calculated by Eqs. (A1)–(A3).
The friction factor (f) used for the Darcy–Weisbach equation [Eq. (16)] depends on the relative roughness of the channels [Eq. (A5)] and the Reynolds number. The Reynolds number from laminar to turbulent flow is calculated by Eqs. (A6)–(A9).
The friction factor (f) in Eq. (16) is calculated by Eq. (35) [45].
When Re1 > Re > Re2, the f is obtained from Eq. (A12), where f1 is obtained from the formula given by Idelchik [46], as shown in Eq. (A13). The Colebrook–White correlation [44] is used to calculate fi, and fn is calculated by iteration. When the error between fi and fn is less than 0.01, it can be assumed that fi = fn. Eqs. (A16)–(A19) use the same calculation method.
When \({{Re}}_{2} < {{Re}} < {{Re}}_{3}\)
When \({{Re}} > {{Re}}_{3}\)
For more information on the above equations, it is recommended to refer to the references cited in Appendix.
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Yu, GP., Cheng, YF., Zhang, N. et al. Multi-objective optimization and evaluation of supercritical CO2 Brayton cycle for nuclear power generation. NUCL SCI TECH 35, 22 (2024). https://doi.org/10.1007/s41365-024-01363-y
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DOI: https://doi.org/10.1007/s41365-024-01363-y