Fast Breeder Reactor (FBR)
University of Fukui
Tsuruga NPP
(JAPC)
JAEA Tsuruga HQ
INSS
Fugen (JAEA)
Tsuruga Peninsula
Mihama NPP (KEPCO)
APWR Site
Monju (JAEA)
Research Center (JAEA)
Professor H. MOCHIZUKI
Research Institute of Nuclear Engineering
University of Fukui
1
Outline
University of Fukui
•
•
•
•
•
Pu production and fuel cycle
Comparison between LWR and FBR
FBRs in the world
Components of FBR
Thermalhydraulic analysis of FBR
2
FBR and LWR
University of Fukui
FBR: Breed nuclear fuel
(238U⇒239Pu.) We can utilize
nuclear fuel for a couple of
CR
thousands.
Fuel
LWR：235U of 0.7% in the uranium ore is
consumed. Uranium 235U will be
consumed within 100 years.
Blanket fuel
238U
239Pu
Liquid sodium
Large core
Temp: ~300℃
High-pressure
Core is small.
Temp. is more
than 500℃.
Atmospheric pressure
FBR
Pu(~20％)+238U(~80％) : MOX
LWR
Fuel
Slightly enriched uranium （ 3～
4％ 235U）
Liquid sodium
Non
Fast neutron
Coolant
water
Moderator
water
Fission
Thermal neutron
3
Fuel cycle
University of Fukui
FBR cycle
LWR cycle
Mine
Uranium
U3O8
FBR
FBR fuel
Depleted
uranium
Enrichment
Depleted
uranium
Enriched U
Recovery U
UF6
Recovery U & Pu
Spent fuel
Fuel fabrication
Recovery U & Pu
Reprocessing Plant
Fuel fabrication
(U
&
MOX
fuels)
HLW
Recovery U & Pu
Reprocessing Plant
Spent fuel
LWR Fuels
LWR
HLW
Underground
storage
Intermediate storage
4
Fission in LWR or Graphite reactor
University of Fukui
Control
Moderator
Water, Graphite
moderation
Fast neutron
10,000 km/s
1/30 of light speed
2.2 km/s
10,000 km/s
235U
has a large fission cross section to a thermal neutron.
Some fast neutrons are absorbed in 238U and produce 239Pu.
5
Neutron irradiation chain of 238U
University of Fukui
15
452
238U
2.7
239U
22
23.5 min
b
disintegration
239Np
37
240U
Half-life period
14.1 h
240Np
Fission cross section
7.2 min
2.35 d
747.4 62 min
239Pu
270
240Pu
289
1012
241Pu
242Pu
361.5
14.4 y
200
18.8
243Pu
90
4.96 h
3.1
（n,g) reaction
241Am
242Am
639.4
243Am
76.7
6
Microscopic cross section of 235U & 238U
University of Fukui
Easiness of fission
From R A Knief, Nuclear Engineering
0.7％
99.3％
Thermal neutron
Fission cross section is
large for thermal neutron.
Fast neutron
Fission cross section
is small for fast
neutron.
7
Cross section of neutron capture of 238U
University of Fukui
8
Number of neutrons produced by one fission
Number of neutrons produced by a fission
University of Fukui
239Pu
When η is less than 2,
breeding is impossible.
241Pu
Thermal neutron
One must be used for
a fission, and the other
one should be used for
breeding.
Some of them escape
from the reactor.
Fast neutron
Energy of neutron (eV)
9
Characteristics of FBR
University of Fukui
• FBR can produce nuclear fuel more than
consumption. Configuration of FBR is
different from LWRs.
• Neutrons are not moderated in order to
breed nuclear fuel efficiently.
• Enrichment of fuel is higher than that of
LWR in order to raise fission probability.
• Fuels should be cooled by good heat
transfer coolant (sodium) because power
density is high.
10
Comparison of reactor vessel between FBR and LWR
University of Fukui
Monju
238MWe
Reactor
vessel is
thin due
to low
system
pressure
Mihama
Unit-3
826MWe
Reactor
vessel is
thick due
to high
system
pressure
11
Comparison of fuel arrangement
between FBR and LWR
University of Fukui
238U+Pu(20%～30%)
Driver fuel
Blanket fuel of 238U is placed
in the peripheral, upper and
lower region of the core in
order to breed effectively.
•Small core
•Short fuel
•Small
diameter fuel
Example：238U（96%）＋ 235U（4%）
•Large core
•Long fuel
•Large diameter
fuel
Enrichment is high in the outer
region of the core in order to
flatten the power distribution.
12
Comparison of fuel assembly
University of Fukui
Length：2.8m
Feul elements：162
Blanket pellets are
inserted in the
cladding.
Length：4.2m
Length：approx. 4m
Effective length：Approx. 3.6m
Weight：670kg (17×17)
13
Comparison of turbine system
University of Fukui
Containment Vessel
Main steam
13MPa
483℃
MSIV
0.8MPa
Low P turbine
MSIV
バイパス弁
B
G Generator
高圧タービン
D Condenser
Sea water
A Condensate pump
0.0042MPa at 30℃
Control valve
6.4MPa
278℃
Feed-water pump Low pressure
High pressure
feed-water
feed-water
heaters
Turbine rotor
heaters
Generator
Cross-over pipe
200℃
Vacuum
25℃
Casing
Feed water heaters
15.7MPa
325℃
Control valve
Main steam
Casing
Extraction
Efficiency: ≈40%
Efficiency: ≈32%
14
Rankin Cycle
University of Fukui
Critical point
347.15 ℃
487℃
22.1MPa C
T
B’
Liquid
~300K
0
328℃
B
A
SA
Mixture
D’
T
Higher energy
C’
Super heated
steam
D
E
Saturation curve
S’C SC
Ｓ
Critical point
647.3 K
22.1MPa
Liq. B’ 280℃
- Receive
Q1
- Release
Q2
- Power output L1
- Pump work
L2
B
0
A
SA
C’
Super
heated S.
D’
Mixture
S’C
E
Ｓ
Q1  iC  iB  Area( BB' C ' CSC S A B) Q1  iC '  iB  Area( BB' C ' SC ' S A B)
Q2  iD  iA  Area( ADSC S A A)
Q2  iD '  i A  Area( AD' SC ' S A A)
L1  L2  iC  iD   iB  iA   Q1  Q2 L1  L2  iC '  iD '   iB  i A   Q1  Q2
F 
L1  L2 Q1  Q2
Area( ABB' C ' CDA)


Q1
Q1
Area( BB' C ' CSC S A B)
L 
L1  L2 Q1  Q2
Area( ABB' C ' D' A)


Q1
Q1
Area( BB' C ' SC ' S A B)
15
FBR & LWR
University of Fukui
Neutron life time
FBR
LWR
10-7 seconds
10-5 seconds
Ratio of delayed neutron 0.34～0.37%
0.55～0.7%
Mean free path
long
short
Coolant
Sodium (low corrosive)
Water (high corrosive)
Fuel
UO2,, PuO2 (Enrichment ～ UO2 (Enrichment 3～
20%）
4%）
Cladding
S.S.
Zircaloy
Dia. of fuel pellet
4～6mm
Approx. 1cm
Outlet coolant
temperature
500～550℃
280～320℃
Temperature difference
130～150℃
15℃（B)～35℃（P)
System pressure
Atmospheric
7MPa（B)、15MPa（P)
Power density
Approx. 300kW/l
Approx. 90kW/l
Burn-up
100,000MWd/t
30,000～60,000MWd/t
Efficiency
Approx. 40%
Approx. 32%
16
Characteristics of sodium
University of Fukui
◆ Sodium is alkali metal which is soft and has metallic color.
Weight of sodium is 0.97 times of water at 20 ºC.
◆Melting point is 98ºC（97.8 ºC ）.
◆Boiling point is 881.5ºC at atmospheric pressure.
Sodium is lighter
than water.
Easily cut by a
knife
Liquid sodium
17
Reaction of sodium with water and air
University of Fukui
◆When sodium reacts with water, hydrogen gas and NaOH are produced.
2Na + 2H2O → 2NaOH+ H2（Hydrogen）＋Heat
Therefore, sodium must be separated from water.
◆Leak speed of sodium is slow due to atmospheric system pressure.
However, sodium reacts with air as shown in photos, and produces a lot of
white alkali aerosol.
18
Blow-down of high-pressure and high-temperature
coolant
University of Fukui
•Blow-down: Discharge of hightemperature and high-pressure
light water
•ECC water injection in order to
cool down the heat-up fuel
•Even a small amount of steam
leak, a jet is very dangerous. This
is a different point compared to a
leak of sodium.
9 Aug 2004 at
Mihama NPP,
5 people were
killed and 6
were seriously
injured.
19
Sodium leak from secondary system on 8 Dec. 1995
University of Fukui
Leak location
IHX
Reactor
Evaporator
Super
heater
Debris of sodium from a
broken thermocouple
Air cooler
Pump for secondary system
20
Reason of superiority of Na among liquid metal
Na
K
University of Fukui
NaK
Li
Pb
Bi
(70/30)
Pb/Bi
Hg
(eutectic)
Melting point(℃)
97.5
62.3
40
186
327.4
271.3
125
-38.9
Boiling point(℃)
881
758
825
1317
1737
1477
1670
357
Vapor pressure(600℃)(mmHg) 26
128
5×10-2
3×10-4
6×10-4
71
0.17
0.034
22(atm)
Neutron absorption cross section
Thermal neutron (barns)
0.505
2.07
Fast neutron (100eV)(mb)
1.1
5(400eV)
1000
Half-life period
15hr.
12.5hr.
0.8sec.
3.3hr.
Thermal conductivity
0.15
0.084
0.07
0.036
4
380
3
60
5days
5.5min.
0.037
0.02
(600℃)(cal/cm/sec/℃)
Specific heat(600℃)(cal/g/℃) 0.3
Density (600℃)(g/cm3)
0.183
1.0
0.038
0.038
0.03
0.81
0.7
0.47
10.27
9.66
12.2
3.4
1.9
1.2
8.8
1.2
1.3
1.2
1.4
47
29.2
78
4.2
178
238
233
169
3
42
Heat transport capability
(4in.φPipe)(C.H.V./ft2℃sec.)
Pumping forth (1/ρ2c3)
Price (￡/ft3)
16
120
40
500
300
730
21
Sodium cooled fast reactors
University of Fukui
Loop type FBR “Monju”
Tank type FBR “Phénix”
Secondary sodium
Super heater
(SH)
Main motor
Primary & Pony motor
circulating
Primary pump
sodium
Turbine
Generator
Air cooler
（AC)
Condenser
Secondary
circulating
pump
Sea water cooler
Evaporator
(EV)
Core
Feed water pump
Intermediate Heat Exchanger
(IHX)
Primary Heat Transport System (PHTS)
Turbine system
Secondary Heat Transport System (SHTS)
22
FBR around the world
University of Fukui
DFR, PFR (Therso)
Super Phénix
(Crays-Malville)
BN-600, 800(Belouarsk)
BOR-60(Dimitrovgrad)
CEFR(Beijing)
BN-350(Aktau)
Phénix (Marcoule)
Monju (Tsuruga)
Joyo (O-arai)
FFTF(Hanford)
EBR-Ⅱ(Idaho falles)
FBTR, PFBR (Kalpakkam)
:Closed
：in operation (including
operation)
23
First power plant in the world (USA)
University of Fukui
EBR－I (Experimental Breeder Reactor)
Coolant was NaK. Four light bulbs were lit up on 20 December
1951.
24
Donreay Fast Reactor, PFR (UK)
University of Fukui
Rating: 60 MWt/15MWe
Coolant: Na-K
Loops: 24
Prototype Fast Reactor
25
Phénix (France)
University of Fukui
Oldest power reactor
in France.
Rating: 565MWt/255MWe
Coolant: Na
Loops: 3
26
Tank-type FBR（Phénix)
University of Fukui
27
Super-Phénix (France)
University of Fukui
Electrical power:
1200MWe
Demonstration
plant in France
・Super-Phénix was sacrificed by Prime minister
Jopspin on 2 February 1998 in order to have a
coraboration between Socialist party and green party.
28
Super-Phénix
University of Fukui
Photo shoot in
side the plant
was allowed after
the workshop at
SPX. This might
be the first and
the last chance.
29
FBTR (India)
University of Fukui
40 MWt /13.2 MWe
Fuel
Mark I ( 25 Nos.)
Mark II ( 13 Nos.)
PFBR test SA
70% PuC + 30% UC
55% PuC + 45% UC
29% PuO2 + 71% UO2
From IAEA-TECDOC-1531
30
PFBR (India)
University of Fukui
01
Main Vessel
02
Core Support Structure
03
Core Catcher
04
Grid Plate
05
Core
06
Inner Vessel
07
Roof Slab
08
Large Rotating Plug
09
Small Rotating Plug
10
Control Plug
11
CSRDM / DSRDM
12
Transfer Arm
13
Intermediate Heat
Exchanger
14
Primary Sodium Pump
15
Safety Vessel
16
Reactor Vault
31
PFBR in 2008
University of Fukui
32
BN600 (Russia)
University of Fukui
Beloyarsk NPP is close to Ekaterinburg.
Pressure tube type reactor
Site for BN800
BN600
33
BN600
University of Fukui
Modular type steam generator
Irradiation of vibro-pack fuel (Dismantled
War head was used.)
From IAEA-TECDOC-1531
34
BN600
University of Fukui
From IAEA-TECDOC-1531
35
CEFR(1/3)
University of Fukui
36
CEFR(2/3)
University of Fukui
37
CEFR(3/3)
University of Fukui
38
Core of “Monju”
University of Fukui
39
Fuel subassembly
University of Fukui
• Handling head: for the
gripper of refueling machine
• Spacer pad: keep
clearance to the adjacent
wrapper tube
• Wrapper tube: keep flow
rate and protect fuel
subassembly
• Entrance nozzle: adjusting
flow rate. Many orifices to
prevent blockage
Length：2.8m
Length：4.2m
40
Shielding plug
University of Fukui
Hole for upper core structure
Hole for refueling machine
41
UIS and refueling machine
University of Fukui
42
Arrangement of initial core
University of Fukui
Driver fuel subassemblies
(fuels for driving the core)
Blanket fuel subassemblies
(fuels for breeding)
Enrichment 20%
Inner core
Outer core
Enrichment 25%
238U
Blanket
Dummy
Neutron source
Control rod
B4C
43
Flow distribution mechanism
University of Fukui
“Monju”
Wrapper tube
Phénix
Core support plate
Orifices of entrance
nozzsle
Slit
High pressure plenum
Entrance nozzle
Connection
pipe
High pressure plenum
Low pressure plenum
Low pressure plenum
44
Fuel subassembly of Fermi reactor
University of Fukui
A fuel melt accident occurred
in October 1966. A part of a
fuel structure fell down at the
inlet of the fuel assembly and
blocked the entrance.
Orifices were provided in
order to prevent total
blockage. This is a lesson
learned from the accident.
45
Piping of primary heat transport system
University of Fukui
Piping is winding in order to absorb stress due to
elongation caused by high temperature coolant flow.
46
Anti-seismic supporting mechanism
University of Fukui
47
Intermediate heat exchanger
University of Fukui
Outlet of secondary side
Primary
Secondary
Flowrate
5120t/h
3730t/h
Inlet temp.
529℃
325℃
Outlet temp.
397℃
505℃
Configuration
of heat
transfer tube
OD 21.7mm,
thickness:1.2mm,
length:6.07m
Number of
HT tubes
3294
Rating
238MW
Height
12.1m
Inlet of secondary side
Approx. 6m
Approx.12m
Inlet of
primary side
Outlet of primary side
48
Heat transfer in IHX
University of Fukui
Outlet of secondary side
100
Inlet of secondary side
[3]
10
[1] Seban & Shimazaki
(Nu=5+0.025Pe0.8 )
Nu
[1]
[2] Martinelli & Lyon
Approx. 6m
(Nu=7+0.025Pe0.8 )
[3] Lubarsky & Kaufman
Approx.12m
(Nu=0.625Pe0.4 )
1
Nu(1) 50MWSG
Nu(1) Joyo
Nu(1) Monju
Nu(2) 50MWSG
Nu(2) Joyo
Nu(2) Monju
Seban-Shimazaki
0.1
1
10
100
Pe
1000
Inlet of
primary side
4
10
5
10
Outlet of primary side
49
Internals of IHX
University of Fukui
50
Primary main pump
University of Fukui
Intake pressure should
be positive in order to
prevent cavitation.
Liquid surface is formed
inside the casing of the
pump. Height of the
pump is restricted by
this surface height.
51
Primary main pump
University of Fukui
Impeller blade
52
Electoro-magnetic pump
University of Fukui
Fabrication of a large
EM pump is difficult.
If one can fabricate a
large EM pump, the
location problem will
be solved.
Maintenance
becomes easy.
53
Steam generator
University of Fukui
140 heat transfer tubes are coiled.
54
Super heater used at 50MW SG facility
University of Fukui
Sodium flow
Inner duct
Helically coiled heat
transfer tube
Water flow
55
Air cooler for auxiliary system
University of Fukui
Design: 15MW, Real rating :20MW
Outlet damper
(controlled with inlet vanes)
Approx.
30m
Heat transfer tubes with fins
~5.3m
~4.5m
~6.5m
Inlet damper
Inlet vanes
Blower
56
H.T. C. of Finned Heat Transfer Tube
University of Fukui
1000
hde
Nu 
k a 100
50 MWSG
Monju
Joyo
Turbulent
+10%
-10%
Data by Jameson
1/3
1/3
Nu/Pr
Carbon S.
Copper
S. S.
Nu/Pr =0.1370Re
0.6702
10
Laminar
1
+20%
1/3
-20%
0.1
10
-3
Nu/Pr =9.796 ×10 Re
100
1000
0.9881
4
10
5
10
Re
57
Inter-subassembly Heat Transfer Model
University of Fukui
Sodium flow in subassembly

t
δg

Center
Inter-wrapper flow
Tk-1
Tk
hd e
Nu 
 5  0.025Pe0.8
kliq
Tk
Tk＋1
k+1th layer
g
1
t


U
kliq  h g
ks
k: thermal conductivity
h: heat transfer coefficient
kth layer
k-1th layer
58
Heat Transfer to the Concerned Channel
University of Fukui
j
Qm


6
n
j
j
N
l
D
z
U
m
,
i
m
i 1

j
Tn ,i
j
 Tm
j: concerned axial mesh
m: concerned channel group
l: width of hexagonal wrapper tube
Dzj: length of mesh j
Nmn,i: number of subassemblies of
channel group n facing to the face i
of channel m

Tn,ij Layer k+1
Tmj To,ij
Layer k
59
Exit temperature of 3rd Layer Subassembly
University of Fukui
560
540
40℃
Temperature
( deg-C
(℃) )
Temperature
520
SSC-L
500
480
Measured
460
440
NETFLOW++ with ISHT model
NETFLOW++ without ISHT model
420
400
0
50
100
150
200
250
300
350
400
Time (sec)
60
Downsizing of FBR
University of Fukui
Volume of reactor building
= 810,000 m3
Prototype FBR “Monju”
Thermal output 714 MWt
Electrical output 280 MWe
Gen-IV FBR (JSFR)
Thermal output 3570 MWt
Electrical output 1500 MWe
61
Combined IHX and pump
University of Fukui
Motor
Pump support
primary out
primary in
NSSS
secondary out
Pump can be withdrawn.
Bellows
DHX
IHX heat transfer IHX support
tubes
Pump
secondary in
62
Heat Transport Systems of Monju
University of Fukui
NETFLOW++ code
NSSS
BOP
Secondary sodium
Super heater
(SH)
Main motor
Primary & Pony motor
circulating
Primary pump
sodium
Turbine
Generator
Air cooler
（AC)
Condenser
Secondary
circulating
pump
Sea water cooler
Evaporator
(EV)
Core
Feed water pump
Intermediate Heat Exchanger
(IHX)
Turbine system
Primary Heat Transport System (PHTS)
Secondary Heat Transport System (SHTS)
63
Calculation model of whole heat transport systems
University of Fukui
[37]
15
[36]
14
[32]
Loop-A
Loop-B
13
9
8
7
[31]
[20]
[38]
[14]
[15]
Air cooler
[33]
[19]
[48]
3
16
-1 Upper plenum
[46]
6 1
-3
4
[30]
1
1
[21]
2
20
21
[25]
3
Loop-C
[41]
19
[43]
[49]
12
[23]
-4
5
1
1
[27]
[8]
[9] [10]
[12]
Pump
to Loop-C
[34]
11
1
Evaporator
[16]
31.41
to Loop-B
Superheater
from
Loop-B,
C
3
Link 1-Link 6: 1st to 6th layer (Inner driver)
Link 7: 7th & 8th layer (Outer driver)
Link 8: 9th to 11th layer (Blanket)
Link 9: Center CR
Link 10: CRs
Link 11: Bypass
24
Low-pressure
turbine
Condense
r
(Pressure
boundary)
Extraction
[45]
[44]
[26]
[35]
IHX
４
High
pressure
plenum
[24]
22
[28]
[11]
[1]～[7]
[42]
[17]
[40]
[39]
17
２
[13]
3
18
[47] 10
Pump
[29]
5
[18]
[22]
to turbine
-2
23
No. 2 feed
water heater
No. 1 feed Feed water
water heater pump
Monju 3-Loop Calculation Model
(Flow boundary)
Deaerator
Drain
Drain
64
University of Fukui
Analytical Model of Turbine
and Feedwater Systems
19
To low pressure
turbine
High pressure turbine
Sodium flow
9
17
16
10
12
11
-1
20
9
21
11
10
13
12
14
15
Super-heaters
25
19
23
Deaerator
18
18
15
Feed
water
13
Separators
5
16
Evaporators
Control valves
17
Loop-A
6
7
6 37
14
4
2
3
8
3
2
3
2
3 34
2
22
Loop-B
24
No. 2 high pressure
Feed water heater
Loop-C
Volume model
8
Feed
water
pump
4
5
3
1
3
1
No. 1 high pressure
Feed water heater
Bold number: volume element
Italic number: link number
Blue number: number of nodes
65
Calculation of turbine and feed water system
University of Fukui
66
Simulation of turbine trip test conducted at “Monju”
University of Fukui
R/V outlet (P) (Test)
IHX outlet (P) (Test)
IHX inlet (S) (Test)
IHX outlet (S) (Test)
R/V outlet (Calc.)
IHX outlet (P) (Calc.)
IHX inlet (S) (Calc.)
IHX outlet (S) (Calc.)
Temperature (℃)
450
400
600
Flowrate (P) (Test)
Flowrate (S) (Test)
Flowrate (P) (Calc.)
Flowrate (S) (Calc.)
500
400
350
300
300
200
250
100
200
0
2000
4000
6000
Time (sec)
8000
Flow rate (kg/s)
500
500
1A1
2F1
3F1
4F1
5F1
6F1
1st
2nd
3rd
4th
5th
6th
0
10000
450
400
1st layer (Test)
2nd layer (Test)
3rd layer (Test)
4th layer (Test)
5th layer (Test)
6th layer (Test)
Layer (Analysis)
layer (Analysis)
layer (Analysis)
layer (Analysis)
layer (Analysis)
layer (Analysis)
350
300
0
2000
4000
6000
Time (sec)
8000
10000
67
Whole heat transport system model of “Joyo”
University of Fukui
-2
[25]
[14]
7
[26]
Pump
Pump
[15]
[21]
Upper plenum
IHX
Air cooler 1
８
[22]
UCS
-1
Air cooler 2
[24]
IHX
5 [19]
[16]
7
-3
Air cooler 3
８
Air cooler 4
4
[12]
[20]
[23]
[18]
3
Pump
Pump
[17]
Joint
Sub-joint
2
[1]-[7]
1
High-pressure
plenum
Check valve
[11] [8]-[10]
6
[13]
Low-pressure
plenum
Link [1]: Center-subassembly
Link [2]: First layer
Link [3]: Second layer
Link [4]: Third layer
Link [5]: 4th layer
Link [6]: 5th layer
Link [7]: Irradiation rigs
Link [8]: Control rods
Link [9]: Inner reflectors
Link [10]: Outer reflectors
Link [11]: Bypass channel
68
Natural circulation after plant trip at “Joyo”
University of Fukui
Initial plant power: 140MW
600
400
Temperature (℃）
550
Calc.
Calc.
Calc.
Calc.
Calc.
350
Primary flowrate A
Secondary flowrate A
Calc.
Calc.
500
300
450
250
400
200
350
150
300
100
250
50
200
0
0
600
1200
1800
2400
3000
Flow rate (kg/s)
Reactor outlet temp (A)
Reactor inlet temp (A)
DHX inlet (A)
DHX outlet (1A)
DHX outlet (2A)
3600
Time (sec)
69
Natural Circulation Analysis of EOL Test
at Phénix Reactor
University of Fukui
IAEA CRP Blind Test
15
[30]
C-loop
12
Pu
mp
[22]
Link 1-4 : 1st to 4th layer (Inner driver)
Link 5, 6: 5th & 6th layer (Outer driver)
Link 7 : Blanket (7th to 8th layer)
Link 8 : CRs
Link 9 ARA
Link 10 : Shielding
Link 11 : Bypass
[21]
14
A-loop [29]
Reheater
9
Pu
Superheater [19]
[18] mp
Upper plenum
4
-1
13
IHX
[23]
[14]
11
Pump
[33]-3
3
1
2
[31]
4
[28]
[12]
3
[
2
2 7
]
Pump
[8]
[1]～[7]
1
[15]
5
[9] [10]
Lower plenum
[13]
[26]
7
[17]
10
[20]
Evaporator
[11]
6
IHX
[16]
8
-2 [32]
1
from Cloop
3
Flow
to
boundary
turbine
(Flow rate
P
b
and
c boundary
enthalpy)Pressure
70

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