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Reactivity and Power Distribution Anomalies. Nuclear Reactor Experiment Group III. Prologue. 2002 IAEA AIRS. Prologue. Financial Efficiency. Life Safekeeping. Table of Contents. RCCA accident analysis. Accident Simulation. Conclusion. Rod bank uncontrolled out (Full Power).

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## Nuclear Reactor Experiment Group III

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**Reactivity and Power**Distribution Anomalies Nuclear Reactor Experiment Group III**Prologue**2002 IAEA AIRS**Prologue**Financial Efficiency Life Safekeeping**Table of Contents**RCCA accident analysis Accident Simulation Conclusion**Rod bank uncontrolled out (Full Power)**RCCA Accident Analysis Reactivity Power Distribution Rod bank uncontrolled out (Low Power) Drop of a single control rod in CBC ANS Cond.II,III Rod bank uncontrolled in**Hot Standby**Hot Shutdown Startup Cold Shutdown Power Operation RCCA Accident Analysis Rod bank uncontrolled out (Full Power) Rod bank uncontrolled out (Low Power) Drop of a single control rod in CBC Rod bank uncontrolled in**Variable List**Net Reactivity Relative Prompt Power Normalized Thermal Power Dist. Average Fuel Temperature Core Coolant Temperature DNBR**2 Group Diffusion Equation**Power & flux relation Define**Multiplication constant**Reactivity Power & flux relation Eigenvalue problem**Accident Simulation**Rod bank uncontrolled out (Power 50%) Rod bank uncontrolled out (Low Power) Drop of a single control rod in CBC Rod bank uncontrolled in**Rod bank uncontr. out (Power 50%)**Condition to Simulate • Operating State : Power (50%) • Duration Time : 130 (s) • Bank D Withdrawal • Initial Core Condition • Temperature(°C) : 537 • Pressure(Pa): 1.56 X 10^7 • Reactivity : 3.66 X 10^-6 • DNBR : 2.05 D D D D**Rod bank uncontr. out (Hot Standby)**Condition to Simulate • Original Target : Neutron Flux Trip • CNS : Absence of Neutron Flux detect function • ->Non neutron flux trip • Alternative proposal • -Malfunction of Bank “D” at Hotstanby state • -Net Reactivity, Thermal power transient • -Etc., Transient features**Rod bank uncontr. out (Hot Standby)**Condition to Simulate • Operating State : Hot Standby • Duration Time : 200 (s) • Bank D Withdrawal • Initial Core Condition • Temperature (°C) : 292 • Pressure(Pa) : 1.56 X 10^7 • Reactivity : 1.7 X 10^-2 • DNBR : 10 D D D D**Rod bank uncontr. out (Hot Standby)**DNB Heat flux predicted applicable correlation DNBR= Reactor local heat flux**Drop of a single control rod in CBC**Condition to Simulate • Operating State : Full Power • Duration Time : 200 (s) • Single Rod Drop • Initial Core Condition • Temperature (°C) : 734 • Pressure (Pa) : 1.55 X 10^7 • Reactivity : 8.16 X 10^-8 • DNBR : 1.34 C**Rod bank uncontrolled in**Condition to Simulate A • Operating State : Full Power • Duration Time : 400 (s) • Bank A Drop • Initial Core Condition • Temperature (°C) : 734 • Pressure(Pa) : 1.55 X 10^7 • Reactivity : 8.16 X 10^-8 • DNBR : 1.34 A A A**Conclusion**• Confirm equations and it’s implications relating to Reactor core • Verify the correlation of RCCA position change and Reactor condition variables • Safety acknowledgement through accident simulation • Unrealistic setup which is not applicable to conservative assumption

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