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Operational Reactor Safety 22.091/22.903 Professor Andrew C. Kadak Professor of the Practice Lecture 7 Design Issues Power Cycles for Nuclear Plants Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 1
Transcript of Operational Reactor Safety - MIT OpenCourseWare€¦ · Operational Reactor Safety 22.091/22.903...
Operational Reactor Safety 22.091/22.903
Professor Andrew C. Kadak Professor of the Practice
Lecture 7 Design Issues
Power Cycles for Nuclear Plants
Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 1
Topics to be Covered
• Design Issues for nuclear plants Kneif (8,9 10)
• Rankine Cycle
– Basic
– Superheat
– Multi-fluid cycles
– Brayton cycle
• Pressure Ratios
Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 2
Reactor Design Interactions
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Reactor Core Design
• Thermal Analysis
– Set inlet and outlet temperature
– Assume radial peaking factor to calculate hot channel coolant temperature
– Assume axial flux profile and engineering factors to calculate hot channel coolant temperature
– Calculate clad surface temperature profile for hot channel assuming a clad surface heat flux and empirical heat transfer coefficient
Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 4
Design Process (2) – Set clad and gap conductance materials and
dimensions
– Calculate fuel surface temperature profile
• Fuel Pin Composition and diameter selection
– For a given fuel material use thermal conductivity and peak temperature to determine limiting heat rate for hot channel
– Set pellet diameter based on fuel fabrication cost
– Recalculate heat fuel and temperature
Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 5
Reactor Design (3) • Core sizing
– Calculate number of fuel pins from core power and length
– Chose geometry and spacing
– Calculate physics parameters – axial and radial power profiles
– Assess safety (reactivity coefficients) and power conversion factor (core lifetime)
– Calculate required coolant velocity
Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 6
Reactor Design (4) • Fuel Cycle Economic Analysis
• Fuel Pin Structural Analysis
• Hydraulic Analysis
– Pressure drops, flow distributions
– Pumping power requirements
• Safety Analysis
– Reactivity coefficients for accident analysis
• Fuel element reliability analysis – fuel stress etc.
• Post Irradiation handling considerations – cooling needs
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Fuel Performance
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Fuel Designs for LWRs
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BWR Fuel Assembly
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PWR Fuel Assembly
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Fuel Rod Design Interactions
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Typical Protective System
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Prof. Andrew C. Kadak, 2008
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Daya Bay PWR – French Design
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Schematic of Plant Design
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Key Reactor Systems
• Reactor Coolant System
• Heat Removal Systems
• Nuclear Support Systems
• Plant Service Systems
• Nuclear Safety Systems
• Balance of Plant
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Power Conversion Systems
Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 17
Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 18
Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 19
Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 20
Temperature Entropy Diagrams
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Basic Rankine Cycle
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Steam Generators
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Rankine Cycle with Feedwater Heaters
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Power Cycles
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Binary Cycle Plants
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Gas Reactor Cycles
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Brayton Gas Cycle - Open
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Perfect Gas Relationships
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Indirect Brayton Open Cycle
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Direct Closed Brayton Cycle
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Indirect Closed Cycle – Gas to Gas
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Indirect Gas to Steam Generator
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Specific Heats of Gases
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Ideal Brayton Cycle
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Non-Ideal Brayton Cycle
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Gas-Steam Reactor Power Plant
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Prof. Andrew C. Kadak, 2008 Department
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Reading and Homework Assignment
1. Read Knief Chapter 8, 9, 10
2. Outside Reading El-Wakil Chapter 2
3. Problems 2.7, 7.4
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Department of Nuclear Science & Engineering Page 44
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22.091 Nuclear Reactor SafetySpring 2008
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