Research Article
Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core
| Number | Tfuel (K) | Twater (K) | ρwater (g∙cm−3) |
| 1 | 300 | 308 | 0.99430 | 2 | 350 | 308 | 0.99430 | 3 | 400 | 308 | 0.99430 | 4 | 450 | 308 | 0.99430 | 5 | 500 | 308 | 0.99430 | 6 | 400 | 338 | 0.98081 | 7 | 400 | 368 | 0.96217 | 8 | 400 | 398 | 0.93926 |
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