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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 - PowerPoint PPT Presentation
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Reactor Experiments
Instructor: Prof. Kune Y. SuhT/A : Sang Hyuk Yoon
Saturday, June 14, 2003Composer : 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 Choi, Sang Gook
• Kim, Chan Soo
• Mun, Seung Hyeon
• Yoon, Ei Sung
• Lee, Yoon Jeong
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
Power Plant System
Control Rod•Choi, Sang gook
•Lee, Yoon Jeong
Control Rod
Grid of the Grid of the Control RodControl Rod
Grid of the Grid of the Control RodControl Rod
GSSSGSSSGSSSGSSS
Control Rod
control element control element drive mechanismdrive mechanism
control element control element drive mechanismdrive mechanism CEACEACEACEA
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
Control Rod•Function
To control the reactivity of the core by quick p
utting and pulling out the control rod
To solve the weak points of CVCS dilusion me
thod
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
Control Rod•Composition
Material of the toxic substance in rod
- B4C
Material of the cladding
- Ni-Cr-Fe 652
Control Rod•Control Rods Accidents 1. Ejection of the control rods
Disorder of rod control equipmentMistake of operator
Disorder of rod control equipmentMistake of operator
Reactivity of the core increasesReactivity of the core increases
Generation of Serious peak power Generation of Serious peak power
Fuel damage, TripFuel damage, Trip
Control Rod•Control Rod accident
2. Drop of all control rods in CBA
Breaken equipmentInterception of electricity
Breaken equipmentInterception of electricity
Reactivity decreasesReactivity decreases
Power generation decreases Power generation decreases
Pressure, Temperature, DNBR changesPressure, Temperature, DNBR changes
Control Rod
0 500 1000 1500 2000-0.0040
-0.0035
-0.0030
-0.0025
-0.0020
-0.0015
-0.0010
-0.0005
0.0000
0.0005R
ea
ctivity
sec
Net reactivity
Control Rod
0 500 1000 1500 2000
292
294
296
298
300
302
304
306
308T
EM
P
sec
Average temperature of Primary loop
Control Rod
0 500 1000 1500 2000
278
280
282
284
286
288
290
292T
em
pe
ratu
re
sec
Core coolant temperature
Control Rod
0 500 1000 1500 200013800000
14000000
14200000
14400000
14600000
14800000
15000000
15200000
15400000
15600000
15800000p
ressu
re
sec
Pressurizer pressure
Control Rod
0 500 1000 1500 2000
5.2x106
5.4x106
5.6x106
5.8x106
6.0x106
6.2x106
6.4x106
Pre
ssu
re
sec
Steam generator Pressure
Control Rod
0 500 1000 1500 20001.2
1.4
1.6
1.8
2.0
2.2
2.4D
NB
R
SEC
DNBR
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.
Turbine•Jeong, Won Chae
•Yoon, Ei Sung
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
Turbine
Scene of Turbine Building inside
Turbine
Scene of Turbine Building inside
Turbine
Turbine
Turbine
The system of the LP TurbineThe system of the LP Turbine
Turbine
The system of the HP TurbineThe system of the HP Turbine
Turbine• Causes of Turbine Trip
1. Overload (Overspeed)
2. Wearing the bearing
3. Solenoid trip
4. Low pressure of condenser
5. The manual trip of turbine
Turbine•Effects of the Turbine Trip
Turbine TripTurbine Trip
Steam dumped by ETSSteam dumped by ETS
Pressure reductionPressure reduction
The boiling point of the feed water is decreasedThe boiling point of the feed water is decreased
The heat removed through the steam generator is decreased
The heat removed through the steam generator is decreased
Turbine•Effects of the Turbine Trip
The temperature of reactor coolant increaseThe temperature of reactor coolant increase
The reactivity of core decrease
The sweeling of the water levelin the Reactor
The reactivity of core decrease
The sweeling of the water levelin the Reactor
Melting down of core <<Serious Accident!!!>>Melting down of core <<Serious Accident!!!>>
DNBDNB
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
Turbine•Anticipation
PrimaryLoop
Secondary Loop
Temperature Increase Decrease
Pressure Increase Decrease
Turbine•Results
Reaction forSAFE
Reaction forSAFE
Turbine TripTurbine Trip
Temp. & Press. Incease in Steam LineTemp. & Press. Incease in Steam Line
Turbine Load = 0Turbine Load = 0
• Heat Exchange Rate Dec.• Water Level Dec.• Pressure Inc.
• Heat Exchange Rate Dec.• Water Level Dec.• Pressure Inc.
S/GS/G
Heat Transf.Rate Inc.
Heat Transf.Rate Inc.
2nd Loop Flow Rate Dec.
2nd Loop Flow Rate Dec.
Feed WaterTemp. Dec.Feed WaterTemp. Dec.
Turbine•Results
Turbine TripTurbine Trip Turbine Load = 0Turbine Load = 0
Turbine•Results
Turbine TripTurbine Trip 2nd Loop Flow Rate Dec.
2nd Loop Flow Rate Dec.
Turbine•Results
• Heat Exchange Rate Dec.• Water Level Dec.• Pressure Inc.
• Heat Exchange Rate Dec.• Water Level Dec.• Pressure Inc.
S/GS/G
2nd Loop Flow Rate Dec.
2nd Loop Flow Rate Dec.
Feed WaterTemp. Dec.Feed WaterTemp. Dec.
S/G Level S/G Prssure
Temp. of FW
Turbine•Results
Temp. & Press. Incease in Steam LineTemp. & Press. Incease in Steam Line• Heat Exchange Rate Dec.• Water Level Dec.• Pressure Inc.
• Heat Exchange Rate Dec.• Water Level Dec.• Pressure Inc.
S/GS/G
Steam Presssure from S/G
Turbine•Results
Turbine TripTurbine Trip
• Heat Exchange • Rate Dec.• Water Level Dec.• Pressure Inc.
• Heat Exchange • Rate Dec.• Water Level Dec.• Pressure Inc.
S/GS/G
2nd Loop Flow Rate Dec.
2nd Loop Flow Rate Dec.
Cold Leg Temp. Inc.Cold Leg Temp. Inc.
Reactivity Dec.Reactivity Dec.
Avg. Temp. Dec.Avg. Temp. Dec.
Hot Leg Temp. Dec.Hot Leg Temp. Dec.
Power Dec.Power Dec.DNBR > 1.3DNBR > 1.3
SAFESAFE
Turbine•Results
•Heat Exchange •Rate Dec.•Water Level Dec.•Pressure Inc.
•Heat Exchange •Rate Dec.•Water Level Dec.•Pressure Inc.
S/GS/G Cold Leg Temp. Inc.Cold Leg Temp. Inc.
Reactivity Dec.Reactivity Dec.
Cold Leg Temp. Reactivity
Turbine•Results
Reactivity Dec.Reactivity Dec.
Power Dec.Power Dec.DNBR > 1.3DNBR > 1.3
SAFESAFE
Relative Power DNBR
Turbine•Results
Avg. Temp. Dec.Avg. Temp. Dec.
Hot Leg Temp. Dec.Hot Leg Temp. Dec.
Power Dec.Power Dec.
Hot Leg Temp. Avg. Temp. of Core
Feedwater Pump•Kim, Chan Soo
•Mun, Seung Hyeon
Feedwater Pump• Function
Main feedwater system sends water to each steam generator(SG) Main feedwater pump circulates secondary water
Feedwater Pump
Feedwater Pump
Feedwater Pump
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)
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
Feedwater Pump• Identification of event and causes
The loss of normal flow(LFW) event may be initiated by losing main feedwater pumps
Feedwater Pump• Sequence of event and system Operation
Decreasing water level and increasing pressure and temperature in the steam generator
Decreasing water level and increasing pressure and temperature in the steam generator
The RCS pressure and temperature rise.The RCS pressure and temperature rise.
Reactor tripReactor trip
Feedwater Pump• Emergency Measure of the Accident
Termination of main steam flowTermination of main steam flow
SG and Reactor Coolant System(RCS) pressurizationSG and Reactor Coolant System(RCS) pressurization
Decrease in core heat rateDecrease in core heat rate
Feedwater Pump
RCS becomes New Steady-state ConditionRCS becomes New Steady-state Condition
Auxiliary feedwater InjectionAuxiliary feedwater Injection
Cooldown by OperatorCooldown by Operator
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.
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.
Feedwater Pump
-200 0 200 400 600 800 1000 1200 1400 16006250000
6260000
6270000
6280000
6290000
6300000
6310000
6320000
S/G
pre
ssu
re#
1[P
a]
Time[sec] L67_1
D
S/G Generator #1
Feedwater Pump
-200 0 200 400 600 800 1000 1200 1400 16006250000
6260000
6270000
6280000
6290000
6300000
6310000
6320000
S/G
pre
ssu
re#
2 [P
a]
Time[sec] L67_1
E
S/G Generator #2
Feedwater Pump
-200 0 200 400 600 800 1000 1200 1400 16006250000
6260000
6270000
6280000
6290000
6300000
6310000
6320000
S/G
pre
ssu
re#
3[P
a]
Time[sec] L67_1
F
S/G Generator #3
Feedwater Pump
-200 0 200 400 600 800 1000 1200 1400 1600
307.55
307.60
307.65
307.70
307.75
307.80
307.85
307.90
307.95
Ave
rag
e te
mp
#1
[C]
Time[sec] L67_1
M
Average Temp. #1
Feedwater Pump
-200 0 200 400 600 800 1000 1200 1400 1600
307.55
307.60
307.65
307.70
307.75
307.80
307.85
307.90
307.95
Ave
rag
e te
mp
#2
[C]
Time[sec] L67_1
N
Average Temp. #2
Feedwater Pump
-200 0 200 400 600 800 1000 1200 1400 1600
-0.5
0.0
0.5
1.0
1.5
S/G
leve
l err
or
sig
na
l
Time[sec] L67_1
AA
S/G Level Error Signal
Feedwater Pump
-200 0 200 400 600 800 1000 1200 1400 1600
1.335
1.340
1.345
1.350
1.355
DN
BR
Time[sec] L67_1
AE
DNBR
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