Operational Reactor Safety
22.091 /22.903
Professor Andrew C. Kadak Professor of the Practice
Lecture 8
Power Cycles for Nuclear Plants Rankine and Brayton
Prof. Andrew C. Kadak, 2008 Page 1
Department of Nuclear Science & Engineering
Topics to be Covered
• Review of Rankine Cycle
– B a s i c
– S uperheat
– M ulti-fluid cycles
• Brayton cycle
• Pressure Ratios
Prof. Andrew C. Kadak, 2008 Page 2
Department of Nuclear Science & Engineering
Important Terms and Concepts
• Enthaply - h = Btu/lbm (heat content)
• Entropy - B tu/ 0 R
p .
• Specific Heat - C B tu/lbm 0 R at constant pressure
• Mass Flow Rate = m - l bm/ h . r
.
• Pressure Ratio - P 2 /P 1 (For g as systems)
• Power – W atts - B tu/hr
• Work - B tu
• Efficiency - ( W t - W p ) / Q in (Heat Added)
Prof. Andrew C. Kadak, 2008 Page 3
Department of Nuclear Science & Engineering
Governing Equations
• Heat Transfer
– M ass flow, specific heat, temperature
– M ass flow, specific enthalpy
– E fficiency factors – h eat loss
• Use of Steam Tables
• Quality
Prof. Andrew C. Kadak, 2008 Page 4
Department of Nuclear Science & Engineering
Rankine Cycle
Thermal Efficiency = Hea t Adde d - H ea t Rejected
Heat Added
Important Equations
Q in = m . (h 1 - h B )
Q in = C p m (T in – T ou )
.
W t = m . . (h 1 - h 2 ) W p = m (h B - h 3 )
Prof. Andrew C. Kadak, 2008 Page 6
Department of Nuclear Science & Engineering
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Rankine Cycle with Feedwater Heaters
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Department of Nuclear Science & Engineering
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ment of Nuclear Science & Engineering Page 8
Depart
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Power Cycles
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Department of Nuclear Science & Engineering
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Binary Cycle Plants
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Department of Nuclear Science & Engineering
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Gas Reactor Cycles
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Department of Nuclear Science & Engineering
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Brayton Gas Cycle - O pen
Department of Nuclear Science & Engineering
Prof. Andrew C. Kadak, 2008 Page 12
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Perfect Gas Relationships
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Indirect Brayton Open Cycle
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Department of Nuclear Science & Engineering
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Brayton Cycle – D irect Closed
2
3
1
4
Prof. Andrew C. Kadak, 2008 Page 15
Department of Nuclear Science & Engineering
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Indirec t Close d Cycl e – Ga s t o G as
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Department of Nuclear Science & Engineering
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Indirect Gas to Steam Generator
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Department of Nuclear Science & Engineering
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Specific Heats of Gases
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Department of Nuclear Science & Engineering
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Ideal Brayton Cycle
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Department of Nuclear Science & Engineering
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Non-Ideal Brayton Cycle
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Department of Nuclear Science & Engineering
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Gas-Steam Reactor Power Plant
Department of Nuclear Science & Engineering
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ent of Nuclear Science & Engineering Page 23
008
Departm
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ment of Nuclear Science & Engineering Page 24
8
Depart
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nt of Nuclear Science & Engineering Page 25
, 2008
Departme
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Reading and Homework Assignment
1. Outside Reading El Wakil Chapters 7, 8
1. Handout Problem
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Department of Nuclear Science & Engineering
Handout Problem
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Department of Nuclear Science & Engineering
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22.091 Nuclear Reactor Safety
Spring 200 8
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