Operational Reactor Safety
22.091 /22.903
Professor Andrew C. Kadak Professor of the Practice
Boiling Water Reactors Lecture 15
Topics to be Covered
• Steam Cycle
• Recirculation
• Chimney
• Steam separation
• Heat removal
• Operating with voids
• Plant systems
• Reactor Protective System
• Safety Systems
B W R Plan t Layou t
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BWR Plant Schematic
BWR Early
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Reactor Assembly
Prof. Andrew C. K
uclea r S c ien ce & Engineering Page 6
adak, 2008
Department of N
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Steam and Recirculation System
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Jet Pumps – Recirculation System
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Steam Separator and Dryer
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Key Systems of BWRs
• Standby Liquid Control System (SLCS)
– For redundant shutdown – c ontains boron
• Reactor Core Isolation Cooling System (RCIC)
– D eals with loss of feedwater flow
• Emergency Core Cooling System (ECCS)
– S afety Relief Valve – A utomatic Depressurization System
– H igh Pressure Coolant Injection System (HPCI)
– L ow Pressure Coolant Injection System (LPCI)
• Control Rod Drive System
– H ydraulic Control Units – from bottom of reactor vessel
• Residua l Hea t Remova l Syste m – deca y hea t remova l
Prof. Andrew C. Kadak, 2008
Department of Nuclea r S c ien ce & Engineering
Page 16
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ECCS
Prof. Andrew C. Kadak, 2008
gineering Page 17
Department of Nuclea r S c ien ce & En
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ADS
ADS Valve
Prof. Andrew C. Kadak, 2008 Page 18
Department of Nuclea r S c ien ce & Engineering
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Reactor Power Control
• Control rods – g ross power changes
• Recirculation Flow - +/- 25 % power – Increase flow – i ncrease power
• Turbine Control – P ressure control - constant
– Generator demands more power – t urbine slows down – p ressure decreases – m ore steam created - increase turbine power –then increase recirculation flow to compensate for reactivity loss.
• Recall BWRs have negative void coefficient and Positive pressure coefficient
Reactor Trip Systems
• High Pressure in Drywell
• Low water level in reactor vessel
• High pressure in reactor vessel
• High neutron flux
• High water level in scram discharge volume (control rods)
• Closing of turbine stop or fast closure of turbine control valves
• Main steam line isolation
• High radiation levels in main steam lines
• Leak detection
• Lo w pressur e i n turbin e inle t
Trip Functions
• Insertion of control rods (hydraulic control units in bottom)
• Nuclear System Isolation
– R eactor Coolant Pressure Boundary
– C ontainment Isolation
– C losed System Isolation
Homework
• Read BWR handouts
• Problem 3.3 El Wakil
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22.091 Nuclear Reactor Safety
Spring 200 8
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