Preliminary Core Design Study of Small Supercritical Fast Reactor with Single-Pass Cooling
Abstract
:1. Introduction
2. Design Targets and Criteria
2.1. Design Targets
- Average core outlet temperature ≥ 500 (°C);
- Average linear heat generation rate (ALHGR) ≥ 15.0 (kW/m);
- Operation cycle length ≥ 720 (days).
2.2. Design Criteria
- Maximum cladding surface temperature (MCST) ≤ 650 (°C);
- Maximum linear heat generation rate (MLHGR) < 39 (kW/m);
- Void reactivity coefficient < 0 (%dk/k/%void).
3. Analysis Method
3.1. Neutronic Calculations
3.2. Thermal-Hydraulics Calculations
4. Core Design
4.1. Neutronic Calculations
4.2. Increasing Average Outlet Temperature by Reducing Fuel Assembly Size
4.3. Proposed Design for SMR Class Super FR
5. Conclusions
Author Contributions
Funding
Acknowledgments
Conflicts of Interest
References
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Fuel rod outer diameter (mm)/Fuel rod pitch (mm) | 10.0/11.0 |
Cladding material/thickness (mm) | advanced stainless steel/0.60 |
Number of fuel rods per assembly | 469 |
Average fuel temperature (°C) | 1200 |
Assembly pitch (mm) | 246.6 |
Channel box thickness (mm)/Gap between assemblies (mm) | 1.0/2.0 |
Heated height (m) | 2.0 |
ALHGR (kW/m)/Operation Cycle Length (Days) | 15.0/720 | |||
---|---|---|---|---|
Core 1 | Core 2 | Core 3 | Core 4 | |
Number of assemblies | 127 | 91 | 61 | 37 |
Core equivalent diameter (cm) | 292 | 247 | 202 | 158 |
Thermal power (MWth) | 1800 | 1280 | 860 | 520 |
Average fuel discharge batch number | 2.1 | 2.3 | 2.0 | 2.1 |
Average fuel discharge burnup (GWd/ton) | 42.4 | 46.4 | 41.0 | 43.1 |
Void reactivity coefficient BOEC/EOEC (beginning/end of equilibrium cycle) (%dk/k/%void) | 0.008/ −0.065 | 0.006/ −0.068 | −0.002/ −0.083 | 0.014/ −0.041 |
Pressure loss (MPa) | 0.030 | 0.033 | 0.036 | 0.045 |
Core 4-1 | Core 4-2 | Core 4-3 | Core 4-4 | |
---|---|---|---|---|
Assembly pitch (cm) | 24.66 | 20.82 | 18.89 | 15.04 |
Number of fuel rods per assembly | 469 | 331 | 271 | 169 |
Number of fuel assemblies | 37 | 61 | 91 | 127 |
Core equivalent diameter (cm) | 158 | 171 | 189 | 178 |
Core thermal power (MWth) | 510 | 670 | 740 | 650 |
Average fuel discharge batch number | 2.1 | 2.0 | 2.3 | 2.1 |
Average fuel discharge burnup (GWd/t) | 43.1 | 39.4 | 41.8 | 44.0 |
Thermal power/Electric power (MW) | 650/285 |
Assembly pitch (cm)/Number of assemblies | 15.0/127 |
Cycle length(days)/Batch number | 720/4.2 |
Average Pu enrichment (wt.%) | 18.8 |
Average/Maximaum fuel discharge burnup (GWd/t) | 84.8/107.1 |
Excess reactivity at BOEC (%) | 5.0 |
Fissile Pu surviving ratio | 0.97 |
Void reactivity coefficient BOEC/EOEC (%dk/k/%void) | −0.009/−0.099 |
ALHGR/MLHGR (kW/m) | 15.1/30.6 |
MCST (°C) | 650 |
Coolant inlet/average outlet temperatures (°C) | 280/502 |
Core pressure loss (MPa) | 0.03 |
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Uchimura, K.; Yamaji, A. Preliminary Core Design Study of Small Supercritical Fast Reactor with Single-Pass Cooling. J. Nucl. Eng. 2020, 1, 46-53. https://doi.org/10.3390/jne1010004
Uchimura K, Yamaji A. Preliminary Core Design Study of Small Supercritical Fast Reactor with Single-Pass Cooling. Journal of Nuclear Engineering. 2020; 1(1):46-53. https://doi.org/10.3390/jne1010004
Chicago/Turabian StyleUchimura, Kyota, and Akifumi Yamaji. 2020. "Preliminary Core Design Study of Small Supercritical Fast Reactor with Single-Pass Cooling" Journal of Nuclear Engineering 1, no. 1: 46-53. https://doi.org/10.3390/jne1010004