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LWR
Plant System
-
1
LWR
Plant
System
1
- BWR Development, ABWR Systems -
July
27 Third Period
July
27
,
Third
Period
T k hi SUMIKAWA
T
a
k
as
hi
SUMIKAWA
Kazuhiro YOSHIKAWA
Hitachi
-
GE Nuclear Energy, Ltd.
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
Hitachi
GE
Nuclear
Energy,
Ltd.
1
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Quiz 1
Q: What does “BWR” stand for?
Boiling
W
Ans.: B :
W
W
ater
Reactor
W
:
R:
Reactor
Reactor
R
:
Wh i h i f b ili
Wh
at
i
s
t
h
e
mer
i
t
o
f b
o
ili
ng water
“in” the Reactor?
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
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1(1).Steam is generated in BWR Reactor
BWR PWR
Steam
PCV
PCV
Turbine
Generator
Fuel
Turbine
Generator
Control
Rod
Pressurizer
a
lizer
c
irculation
m
p
Generators
Steam
Steam
1 loop
2 loops
Suppression Pool
Condenser
Water
Control Rod
(CR)
Condenser
Turbine
Generator
Water
Fuel
Deminer
a
Re
c
Pu
m
Feed water Pump
Circ. Water Pump
Feed water Pump
Circ. Water Pump
Demineralizer
Reactor
Reactor
PCV: Primary Containment Vessel
Merits of boiling water in the Reactor are …
Compact PCV; No Steam Generators
Simple Configuration;
Direct cycle (only 1 loop)
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
3
Simple Configuration;
Direct cycle (only 1 loop)
Easy Control; Void Effect can be used for Power Control
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1(2).Features of BWR
Allowance of Boiling in Reactor
Pressure Vessel
Small size
Reactor Pressure
Vessel
・No Steam Generators in PCV
・Suppression Pool
Si l fi ti
Si
mp
l
e
con
fi
gura
ti
on
・Direct cycle (only 1 loop)
E i
E
asy
operat
i
on
・Void Effect is used for the Power Control
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2(1). Evolution of BWR
We want BWR plant to be …
• Extremely safe
• Competitive in costs
How
should we improve BWR to achieve those?
How
should we improve BWR to achieve those?
1. Simpler configuration
Reduce
trouble risk
2. Enhancing output
power
Reduce
trouble risk
⇒Extremely safe
Reduce material
power
⇒
Competitive in costs
Reduce material
Shorten construction
period
⇒Com
p
etitive in costs
Competitive in costs
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2(2). History of BWR
(Sweden)
(West Germany)
Oskarshamn‐1,2 Forsmark‐1,2 Forsmark‐3
Oskarshamn‐3
Europe
(West
Germany)
(Wurgassen) Philippsburg‐1
Isar‐1
Gundremmingen‐B,C
Krunmmel‐1
d
Dresden‐1Oyster
Creek
Dresden
‐2
Vermont
Yankee
LaSalle‐2GrandGulf‐2
Unite
d
States
Japan
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2(3).BWR Reactor is being simpler.
BWR
3/4/5
BWR
‐
2
SaferandMorecost‐eff ective
ABWR
BWR
‐
1
BWR
‐
3/4/5
BWR
‐
2
Steam Drum
ABWR
ABWR:Advanced Boiling
WaterReactor
BWR
‐
1
???
JetPump
6Recirculation
InternalPump
SteamGenerator
loops
MultipleCircles
DeletedSteamGeneratorsand
2Recirculation
loops
Reductionof
DeletedRecirculation
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
7
(Boiler&Steam
Generator)
aSteamDrum
Recirculationloopsusing
JetPumps
loopsusingInternal
Pumps
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2(4).BWR is enhancing its output power
while keeping its containment size.
Morecost‐effective
MARK‐Ⅰ
(BWR‐3/4)
RCCV:ReinforcedConcrete
ContainmentVessel
MARK‐Ⅱ
(BWR‐5)
RCCV
(ABWR)
PCV type
??
70m
58m
61m
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
52m
8
57m
55m
Output
power
1100MWe
1300MWe(ABWR)
780MWe
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2(5).BWR is enhancing its output power
)
ABWR
U
T(MWe
)
1000
BWR-5
ABWR
OUTP
U
BWR-3
BWR-4
BWR-2
Now let
’
s see the system of ABWR the
2000
YEAR
1960 1970 1980 1990 2010
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
9
Now let s see the system of ABWR
,
the
latest type of BWR in commerce.
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Overview of ABWR Systems
ABWR
Power
Generation
St
Safety Systems Auxiliary
Systems
S
ys
t
ems
Nt id
Nt id
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
10
N
ex
t
per
i
o
d
N
ex
t
per
i
o
d
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3.Power Generation Systems of ABWR
3-1 How is steam generated in ABWR?
(RPV)
3-2 How is electricity generated with steam in ABWR?
(MS, Turbine, MSH, Condenser, FDW)
3-3 How is the output power controlled in ABWR?
(CRD, RRS)
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
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3.Power Generation Systems of ABWR
3-1 How is steam generated in ABWR?
(RPV)
3-2 How is electricity generated with steam in ABWR?
(MS, Turbine, MSH, Condenser, FDW)
3-3 How is the output power controlled in ABWR?
(CRD, RRS)
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
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3-1 How is steam generated in ABWR?
Two functions of RPV are
Two functions of RPV are
…
Main Steam
Normal Water Level
Feed Water
Core
(Nuclear Fuel)
Core
(Nuclear
Fuel)
Reactor
Steam Generator
Extracts heat from the core
Extracts
heat
from
the
core
Same as PWR
Different from PWR
(PWR has some Steam
Generators)
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
13
RPV
(Reactor Pressure Vessel)
Generators)
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3-1 How is steam generated in ABWR?
Two functions of RPV are
Two functions of RPV are
…
Main Steam
Normal Water Level
Feed Water
Core
(Nuclear Fuel)
Core
(Nuclear
Fuel)
Reactor
Steam Generator
Extracts heat from the core
Extracts
heat
from
the
core
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
14
RPV
(Reactor Pressure Vessel)
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3-1 How is steam generated in ABWR?
Water is boiled in the Core
Water is boiled in the Core
.
Normal Water Level
Core
(Nuclear Fuel)
Steam and Hot water
Boiling
Let’s check out the
Core
(Nuclear
Fuel)
Cool water
detail of the Core!
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
15
RPV
(Reactor Pressure Vessel)
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3-1 How is steam generated in ABWR?
Bundles of Fuel and Control Rods are
Bundles of Fuel and Control Rods are
located in the Core.
Cross-section view of
Fuel Bundles
Fuel
Bundles
and Control Rod
Core
Cross-section view of the Core
□ Fuel Bundle × 872 + Control Rod × 205
NMi
○
PR
SR
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
16
N
eutron
M
on
i
tor :
○
P
ower
R
ange ■
S
tartup
R
ange
△ Neutron Source
RPV
Fuel
Bundle
Control
Rod
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3-1 How is steam generated in ABWR?
Two functions of RPV are
Two functions of RPV are
…
Main Steam
Normal Water Level
Feed Water
Core
(Nuclear Fuel)
Core
(Nuclear
Fuel)
Reactor
Steam Generator
Extracts heat from the core
Extracts
heat
from
the
core
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
17
RPV
(Reactor Pressure Vessel)
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3-1 How is steam generated in ABWR?
Water/Steam flow in RPV
Steam Dryer
removes moisture from
Pressure: 7MPa
Temperature:280℃
Pressure: 7MPa
Temperature:280℃
Water/Steam flow in RPV
Steam
removes
moisture
from
steam from the
separators.
Main Steam 7,600t/h
Feed Water
Remove
droplet from
steam
Steam
Separator
separates steam and
water from the core.
7,600t/h
steam
Droplets damage the
turbine blades.
Feed Water
nozzle
Core Flow
(Water and Steam)
52,200t/h
Separate
Core Flow
Downcomer Flow
(
Water
)
Core
Flow
and
Downcomer
Flow
Shroud
separates Core
Flow and
Downcomer Flow.
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
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52,200 t/h
Feed Water nozzle
cannot be located at
the bottom of RPV.
※EachnumericalvalueisbasedonABWR.
RPV
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3-1 How is steam generated in ABWR?
Shroud separates
Downcomer
flow and
Shroud separates
Downcomer
flow and
Core flow
Steam Dryer
S
hr
oud
Steam
Separator
8m
S oud
Shroud
Core (Fuel)
Shroud
Downcomer
Core flow
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
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flow
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3-1 How is steam generated in ABWR?
Steam Separator separates steam from
Steam
Steam Separator separates steam from
water.
Steam Dryer
Water
Steam (still wet)
Steam
Separator
Water
Water level
Two phase
flow
Steam and Water
Separator
Core (Fuel)
5m
Vanes
Standpipe
5m
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Standpipe
Water
Steam Separator
Steam Separators
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3-1 How is steam generated in ABWR?
Steam Dryer removes moisture from
Steam Dryer removes moisture from
steam.
Steam
Dryer
Dry Steam
Steam
Separator
Wet Steam
Drain
S
Core (Fuel)
2m
S
team Flow
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Drain
Steam Dryer
Steam Dryer
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3-1 How is steam generated in ABWR?
Reactor Internals
1 Vent and Head Spray
2 Steam Dryer
3 Steam Outlet Flow Restrictor
4
Steam Separators
1
Reactor Internals
7.1m
4
Steam
Separators
5 RPV Stabilizer
6 Feedwater Sparger
7 Shutdown Cooling Outlet
8 Low Pressure Flooder (LPFL) and
Shutdown Coolin
g
Floode
r
2
Steam
Dr
y
er
g
9 High Pressure Core Flooder (HPCF) Sparger
10 HPCF Coupling
11 Top Guide
12 Fuel Assemblies
13 Core Shroud
21m
3
4
5
6
8
y
14 Control Rod
15 Core Plate
16 In-Core Instrument Guide
17 Control Rod Guide Tubes
18 Core Differential Pressure Line
7 9
10
11
12
14
Steam
Separator
19 Reactor Internal Pumps (RIP)
20 Thermal Insulation
21 Control Rod Drive Housings
22 Fine Motion Control Rod Drives
23 RIP Motor Casing
16
13
15
17
18
19
20
Core
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
24 Local Power Range Monito
r
22
20
21
22
23
24
出典:社団法人 火力原子力発電技術協会 「火原協会講座28 原子力発電所-全体計画と付属設備- (改訂版)」
Core
Shroud
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3.Power Generation Systems of ABWR
3-1 How is steam generated in ABWR?
(RPV)
3-2 How is electricity generated with steam in ABWR?
(MS, Turbine, MSH, Condenser, FDW)
3-3 How is the output power controlled in ABWR?
(CRD, RRS)
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
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3-2 How is electricity generated with steam in ABWR?
System around Turbine side
System around Turbine side
MS: transfers steam from Reactor to Turbine.
Turbine
:
extracts rotational energy from steam
nanka
Turbine
:
extracts
rotational
energy
from
steam
Generator:converts mechanical energy to electrical energy
Condenser: condenses steam into water.
FDW: heats and transfers water to the Reactor.
ABWR
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
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3-2 How is electricity generated with steam in ABWR?
Functions of Main Steam System (MS)
1. Transfers steam from the Reactor to the Turbine.
2
Isolates the steam source RPV from the Turbine
Functions of Main Steam System (MS)
How?
2
.
Isolates
the
steam
source
,
RPV
,
from
the
Turbine
.
3. Protect RPV from its overpressure.
PCV
Main Steam S
y
stem
(
MS
)
Steam
Steam
y()
Steam
RPV
(
Steam source
)
Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved.
25
()