NUCE 402: Introduction to Nuclear System and Operation Lecture 6 PDF
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Khalifa University
Dr. Ahmed Alkaabi
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Summary
This lecture discusses aspects of nuclear system design and operation with a focus on heat removal via boiling. It covers thermal resistance, boiling regimes, and design considerations including critical heat flux. It also presents relevant correlations for nuclear systems.
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NUCE 402: Introduction to Nuclear System and Operation Chapter 3.2 (Heat Removal from Nuclear Reactors – Boiling) Dr. Ahmed Alkaabi Previous Lectures Newton’s law of cooling q h(Tc Tb ) Total thermal resistance...
NUCE 402: Introduction to Nuclear System and Operation Chapter 3.2 (Heat Removal from Nuclear Reactors – Boiling) Dr. Ahmed Alkaabi Previous Lectures Newton’s law of cooling q h(Tc Tb ) Total thermal resistance Tb a b 1 R 2k f A kc A hA Tm Tb q 1 ln( 1 b / a) 1 R R 4k f H 2kc H hA Temp. along the channel z V f V f cos( Tc Tb Rh qmax ) qmax z H Tb Tb 0 1 sin( ) c p H z V f cos( ) Tm Tb Rqmax H Heat transfer coefficients Dimensionless numbers High Re value for turbulent flow k h 0.023( ) Re 0.8 Pr 0.4 D hDe cp De Re e Nu Pr k k Dittus-Boelter Eq. 2 Boiling Advantage of boiling Lower coolant pressure More heat transfer to coolant Lower cladding temperature Tb BWR (boiling water reactor) Allows extensive boiling Direct steam cycle PWR (pressurized water reactor) Allows limited boiling to enhance heat transfer Bulk water is subcooled => Indirect steam cycle 3 Boiling Regimes Boiling patterns Conduction and radiation heat transfer Experimentally measured => large reduction in Change surface T of heated rods heat transfer Measure heat flux Observe boiling patterns Departure from nucleate Bubbles form on the surface imperfection => boiling (DNB) to film boiling carried away to the bulk coolant => bubbles condensed (Tb < Tsat) Flow velocity More effective heat transfer Bubbles form on the surface imperfection => Convection carried away to the bulk coolant => bubbles dominate persist (Tb = Tsat) 4 Boiling Crisis Departure from Nucleate Boiling (DNB) Nucleate boiling => film boiling Heated rods are exposed to steam vapor Lower heat transfer Rapid increase in fuel temp. Critical heat flux (CHF) Correlations for CHF Subcooled boiling Jens and Lottes Bulk boiling GE 5 Boiling Patterns Boiling patterns Experimentally measured Change surface T of vertical heated pipes Observe changes in flow patterns 6 Boiling Channels BWR Saturated boiling P = 1035psia, Tsat = 550oF A/B 7 Thermal Design of Reactor Design Philosophy Fission product should remain within the fuel Cladding integrity is the pre-requisite Fuel must not melt Important temperatures Melting temp. UO2: ~5000oF (2760oC) vs. Tm ~ 4500oF (2480oC) UCN: ~6500oF (3600oC) Metal U: ~2070oF (1132oC) Temp. for significant fission gas release: ~750oF for met-U DNB ratio (DNBR) Safety margin to prevent DNB Min. 1.9 for BWR Min. 1.3 for PWR qc DNBR qactual Hot channel factor (HCF) q F max F FN FE qav 8 Thermal Design of Reactor qc qmax DNBR F F FN FE qactual qav FN Reactor Power A P qav Fqav qmax qc qc Min. DNBR = q max qav qmax F F (min. DNBR) qc A A P qav F (min. DNBR) To achieve maximum power Increase critical heat flux Decrease hot channel factor Flatten the flux shape Design proper enrichment distribution => fuel loading pattern Lower min. DNBR Need greater confidence with extensive technical justification 9 Summary Heat generation in reactor Heat removal Conduction & Convection T T Tb q m b Thermal resistance R R a b 1 1 ln( 1 b / a) 1 R 2k f A kc A hA 4k f H 2kc H hA k Heat transfer coefficients h 0.023( ) Re 0.8 Pr 0.4 Dittus-Boelter Eq. De Boiling regime Flow patterns DNBR & HCF qc qmax DNBR F qactual qav qc A A P qav F (min. DNBR) 10