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Reactor Experiments

Reactor Experiments. Instructor: Prof. Kune Y. Suh T/A : Sang Hyuk Yoon Saturday, June 14, 2003 Composer : Team F. Contents. Members and Malfunction Nuclear Power Plant System Drop of All Control Rod in CBA Turbine Trip FW Pump. Members of Team F. Members of Team F Jeong, Won Chae

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Reactor Experiments

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  1. Reactor Experiments Instructor: Prof. Kune Y. Suh T/A : Sang Hyuk Yoon Saturday, June 14, 2003 Composer : Team F

  2. Contents • Members and Malfunction • Nuclear Power Plant System • Drop of All Control Rod in CBA • Turbine Trip • FW Pump

  3. Members of Team F • Members of Team F • Jeong, Won Chae • Choi, Sang Gook • Kim, Chan Soo • Mun, Seung Hyeon • Yoon, Ei Sung • Lee, Yoon Jeong

  4. Malfunction • A-1 Drop of All Control Rods in CBA • Choi, Sang Gook & Lee, Yoon Jeong • J-55 Turbind Trip • Jeong, Won Chae & Yoon, Ei Sung • L-67 FW Pump Trip • Kim, Chan Soo & Mun Seung Hyeon

  5. Power Plant System

  6. Control Rod • Choi, Sang gook • Lee, Yoon Jeong

  7. Control Rod Grid of the Control Rod GSSS

  8. Control Rod control element drive mechanism CEA

  9. Control Rod • Methods to Control the Activity in Core • Dilusion by Chemical and Volume Control System • Boric acid is dissloved • But the reaction is slow • Using the Control Rods

  10. Control Rod • Function To control the reactivity of the core by quick putting and pulling out the control rod To solve the weak points of CVCS dilusion method

  11. Control Rod • Composition Totally 81 rods • Shut Down group A,B • Regulating Control group • Part Strength Control group Control Element Drive Mechanism – Magnetic Forced Mechanism

  12. Control Rod • Composition Material of the toxic substance in rod - B4C Material of the cladding - Ni-Cr-Fe 652

  13. Control Rod • Control Rods Accidents 1. Ejection of the control rods Disorder of rod control equipment Mistake of operator Reactivity of the core increases Generation of Serious peak power Fuel damage, Trip

  14. Control Rod • Control Rod accident 2. Drop of all control rods in CBA Breaken equipment Interception of electricity Reactivity decreases Power generation decreases Pressure, Temperature, DNBR changes

  15. Control Rod Net reactivity

  16. Control Rod Average temperature of Primary loop

  17. Control Rod Core coolant temperature

  18. Control Rod Pressurizer pressure

  19. Control Rod Steam generator Pressure

  20. Control Rod DNBR

  21. Control Rod • Conclusion • Drop of all control rods in CBA • Output of whole core power decreases • average temperature decreases • reactivity increases(feedback effect) • the reason of reactivity, DNBR movement • According time goes, temperature and pressure decrease. The accident stops.

  22. Turbine • Jeong, Won Chae • Yoon, Ei Sung

  23. Turbine • Function To convert the steam which is made in the steam generator to energy When the steam expands through the nozzle and blades of a turbine to a condenser, it rotates the rotor of the turbine blades, which links to the axis of the generator

  24. Turbine Scene of Turbine Building inside

  25. Turbine Scene of Turbine Building inside

  26. Turbine Turbine

  27. Turbine The system of the LP Turbine

  28. Turbine The system of the HP Turbine

  29. Turbine • Causes of Turbine Trip • Overload (Overspeed) • Wearing the bearing • Solenoid trip • Low pressure of condenser • The manual trip of turbine

  30. Turbine • Effects of the Turbine Trip Turbine Trip Steam dumped by ETS Pressure reduction The boiling point of the feed water is decreased The heat removed through the steam generator is decreased

  31. Turbine • Effects of the Turbine Trip The temperature of reactor coolant increase The reactivity of core decrease The sweeling of the water level in the Reactor DNB Melting down of core <<Serious Accident!!!>>

  32. Turbine • ETS (Emergecy Trip System) Interrupting the supply of steam and discharging it if turbine is tripped Functioning in mechanical or by the electrical signal from the detector

  33. Turbine • Anticipation

  34. Turbine • Heat Exchange • Rate Dec. • Water Level Dec. • Pressure Inc. S/G Feed Water Temp. Dec. • Results Turbine Trip Turbine Load = 0 2nd Loop Flow Rate Dec. Reaction for SAFE Heat Transf. Rate Inc. Temp. & Press. Incease in Steam Line

  35. Turbine • Results Turbine Trip Turbine Load = 0

  36. Turbine • Results 2nd Loop Flow Rate Dec. Turbine Trip

  37. Turbine • Heat Exchange • Rate Dec. • Water Level Dec. • Pressure Inc. S/G • Results 2nd Loop Flow Rate Dec. Feed Water Temp. Dec. Temp. of FW S/G Level S/G Prssure

  38. Turbine • Heat Exchange • Rate Dec. • Water Level Dec. • Pressure Inc. S/G • Results Temp. & Press. Incease in Steam Line Steam Presssure from S/G

  39. Turbine • Heat Exchange • Rate Dec. • Water Level Dec. • Pressure Inc. S/G • Results Turbine Trip Cold Leg Temp. Inc. Reactivity Dec. 2nd Loop Flow Rate Dec. DNBR > 1.3 Power Dec. SAFE Hot Leg Temp. Dec. Avg. Temp. Dec.

  40. Turbine • Heat Exchange • Rate Dec. • Water Level Dec. • Pressure Inc. S/G • Results Cold Leg Temp. Inc. Reactivity Dec. Cold Leg Temp. Reactivity

  41. Turbine Reactivity Dec. DNBR > 1.3 Power Dec. SAFE • Results Relative Power DNBR

  42. Turbine Power Dec. Hot Leg Temp. Dec. Avg. Temp. Dec. • Results Hot Leg Temp. Avg. Temp. of Core

  43. Feedwater Pump • Kim, Chan Soo • Mun, Seung Hyeon

  44. Feedwater Pump • Function Main feedwater system sends water to each steam generator(SG) Main feedwater pump circulates secondary water

  45. Feedwater Pump

  46. Feedwater Pump

  47. Feedwater Pump

  48. Feedwater Pump • Scram of Indiviual Main Feedwater Pump 1. Lubricating Oil Low Pressure(0.62kg/cm2) 2. Turbine Overspeed(~4928RPM) 3. Condenser Low Vacuum Level(480.6mmHg) 4. Impellent Force Bearing Excess Abrasion 5. Low Inspiration Pressure(Lo-NPSH)(15.5kg/cm2)

  49. Feedwater Pump • Emegency Stop of All Main FW Pump 1. Safety Injection Signal 2. SG High Level 3. All condenser Pump Trip 4. Pump Release Header High Pressure

  50. Feedwater Pump • Identification of event and causes The loss of normal flow(LFW) event may be initiated by losing main feedwater pumps

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