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 Kim, Chan Soo
Choi, Sang Gook
Kim, Chan Soo
Mun, Seung Hyeon
Yoon, Ei Sung
Lee, Yoon Jeong

4. Malfunction Choi, Sang Gook & Lee, Yoon Jeong
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. The system of the LP Turbine

28. 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 Primary Loop Secondary Loop Temperature Increase
Decrease
Pressure

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

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

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

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

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

42. Turbine Results Avg. Temp. Dec. Hot Leg Temp. Dec. Power Dec.
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

51. Feedwater Pump Sequence of event and system Operation
Decreasing water level and increasing pressure
and temperature in the steam generator
The RCS pressure and temperature rise.
Reactor trip

52. Feedwater Pump Emergency Measure of the Accident
Termination of main steam flow
SG and Reactor Coolant System(RCS) pressurization
Decrease in core heat rate

53. Feedwater Pump RCS becomes New Steady-state Condition
Auxiliary feedwater Injection
Cooldown by Operator

54. Feedwater Pump Analysis of Effects and Consequences
Maximum RCS pressure and fuel integraty for the LFW is less than that for the loss of condenser vacuum event(LOCV)
The initial Departure from nucleate boiling rate (DNBR) is the minimum DNBR
The minimum DNBR remains above 1.30.

55. Feedwater Pump Conclusion
The RCS pressure remains below 19.5MPa and the SG pressure remains below 9.6MPa
Thus, ensuring fuel cladding and secondary system integraty
[Assumtion] The only one pump would die.

56. Feedwater Pump
S/G Generator #1

57. Feedwater Pump
S/G Generator #2

58. Feedwater Pump
S/G Generator #3

59. Feedwater Pump
Average Temp. #1

60. Feedwater Pump
Average Temp. #2

61. Feedwater Pump
S/G Level Error Signal

62. Feedwater Pump
DNBR