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

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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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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

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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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Reading and Homework Assignment

1. Read Knief Chapter 8, 9, 10

2. Outside Reading El-Wakil Chapter 2

3. Problems 2.7, 7.4

Prof. Andrew C. Kadak, 2008

Department of Nuclear Science & Engineering Page 44

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22.091 Nuclear Reactor SafetySpring 2008

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