Critical Heat Flux & DNBR Margin Calculator
Calculate Departure from Nucleate Boiling Ratio (DNBR), Critical Heat Flux ($q''_{CHF}$), fuel rod heat transfer regime, and thermal margin in PWR reactor cores.
Subchannel Hydraulic & Thermal Parameters
Typical PWR: 155 bar (2250 psia)
T_sat - T_coolant at hot spot
Fuel rod bundle subchannel
Peak local linear heat rate
Thermal Margin & DNBR Ratio
Departure from Nucleate (DNBR)
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Critical Heat Flux (q''_CHF)
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Regulatory Limit
≥ 1.30 DNBR
Boiling Regime
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Overpower Room
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Thermal-Hydraulic Safety Assessment
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