verification tests performed for development of an integral type … · 2007. 6. 12. · 9database...
TRANSCRIPT
April 18 2007April 18 2007
SiSi--Hwan KimHwan Kim
Verification Tests performed for Development of an Integral Type Reactor
KAERI
SeawaterPotable water
Electricity
Desalination Plant
IntakeFacilities
SMART Desalination Plant
CondensatePump
Brine BlowdownPump
DistillatePump
To Outfall
Steam Supply
FeedSeawater
FinalCondenser
FlashCondenser
Main Ejector
Scale Inhivitor
Feed Water
1st Effect 2nd Effect 3rd Effect Last Effect
Vent Ejector
Steam
PlantSMART
SteamTransformer
System integrated Modular Advanced ReacTor
KAERI
SMART Design
Enhance safety comparing with existing PWR
Shorten construction period
Reduce liquid radioactive wastes
CHARACTERISTICS
Small sized integral type Pressurized Water Reactor
Elimination of the possibility of LBLOCA
Self controlled pressurizer by a non-condensable gas
Low power density and Boron free core
Passive system for the decay heat removal
Simplification of system/components
DESIGN CONCEPT
MCP CEDM
Steam Generator
Pressurizer
Core
Displacer
Reactor Vessel
Annular Cover
Side Screen
KAERI
Experiments for the SMART Program
Integral Effect Tests: VISTA
Separate Effect TestCore and Steam Generator Flow Distribution Test
Two-phase Critical Flow with Nitrogen Gas Test
Critical Heat Flux Test
Flow Instability Test
Thermal Mixing and Heat Transfer Test
Fuel Assembly Pressure Drop Test
Major Components (MCP,CEDM,SG) Performance Test
KAERI
Integral Test
VISTA Facility1/1-height, 1/96-volume of Prototypic SMART, SMART-P
Design pressure/temperature : 17.2 MPa/350 oC
Nominal core heater power : 682 kW (Max. 819 kW)
PurposesOverall T-H performance during normal operation (start-up, heat-up, cooldown)
PRHR test during natural circulation
Investigation for accident Scenarios
Database for design optimization of SMART reactor and code validation
VISTA : Experimental Verification by Integral Simulation of Transients and Accidents
KAERI
SMART vs. VISTA Design
Steam Generator
ReactorVessel
Pressurizer
GasCylinder
MCP
SG
Core
CEDM
PZR
Shielding
MCP
ReactorVessel
••Scale LawScale Law
KAERI
VISTA Facility
KAERI
Thermal Hydraulic Behavior during LOFA
0
100
200
300
400
500
600
700
800
0 50 100 150 200 250 300 350 4000
20
40
60
80
100
120
140
160
180
Pres
sure
(bar
)
Time(sec)
: PT-BPV-01, Primary pressure : Total power
H-LOFA-100H-T
Pow
er(k
W)
High PZR pressure trip
Loss of coolant flow @111sec100% core power & High MCP speed
Rx is tripped by the HPP Trip signal @117secHPP setpoint : 16.44MPa
After trip(@117sec)MCP trips and natural circulation of primary coolant is obtained(10%)Primary system slowly cools down by the PRHRS
0 100 200 300 400200
220
240
260
280
300
320
340
360
380
400
Tem
pera
ture
(o C)
Time(sec)
TC-BPV-01 TC-DWN-01 Avg.Temp
H-LOFA-100H-T
0 50 100 150 200 250 300 350 4000
1
2
3
4
5
Flow
rate
(kg/
s)
Time(sec)
FE-DWN-01H-LOFA-100H-T
KAERI
Thermal Hydraulic Behavior during CEA Ejection Accident
0 200 400 600 800 10000
1
2
3
4
5
Flow
rate
(kg/
s)
Time(sec)
FE-DWN-01H-CRWD-100-T
0 200 400 600 800 1000200
220
240
260
280
300
320
340
360
380
400
Tem
pera
ture
(o C)
Time(sec)
TC-BPV-01 TC-DWN-01 Avg.Temp
H-CRWD-100-T
Power step increase from 723kW to 760kW @170sec100% core power & High MCP speed
Primary pressure increases until it reaches HPP trip setpoint (16.44MPa) After trip(@577sec)
MCP trips and natural circulation of primary coolant is obtained (10%)Primary system slowly cools down by the PRHRS
0
100
200
300
400
500
600
700
800
0 200 400 600 800 10000
20
40
60
80
100
120
140
160
180
Pre
ssur
e(ba
r)
Time(sec)
: PT-BPV-01, Primary pressure : Total power
H-CRWD-100-T
Pow
er(k
W)
High PZR pressure trip
KAERI
Natural Circulation Analysis by MARS 3.0
MARS 3.0 code1-D and 3-D system analysis code for thermal hydraulic analysis of the light water reactor transients
Developed by consolidating and restructuring the RELAP5/MOD3.2 and COBRA-TF codes
SMART specific models Helically coiled SG
Pressurizer with non-condensable gas
Performed natural circulation analysis Comparison of RELAP5/MOD3 results
Data of VISTA experiment
KAERI
Natural Circulation Analysis by MARS 3.0
0 500 1000 1500 20000
2
4
6
8
10
12
14
16
Experiment Calculation
Time, sec
Pres
suriz
er p
ress
ure,
MPa
0 500 1000 1500 20000
1
2
3
4
5
6
7
8
Experiment Calculation
Time, secSG
sec
onda
ry p
ress
ure,
MPa
0 500 1000 1500 2000400
450
500
550
600
Experiment-inlet Experiment-outlet Calculation-inlet Calculation-outlet
Time, sec
SG p
rimar
y te
mpe
ratu
re, K
Secondary Pressure Secondary Temperature
0 500 1000 1500 20000.0
0.1
0.2
0.3
Experiment Calculation
Seco
ndar
y Fl
ow, k
g/s
Time, sec
Secondary Flow
0 500 1000 1500 20000
1
2
3
4
5
6
7
8
Experiment Calculation
Time, sec
PRH
R P
ress
ure,
MPa
0 500 1000 1500 2000250
300
350
400
450
500
550
600
Cal-inlet Cal-outlet Cal-sat temp
Time, sec
Hx
in-o
ut te
mp,
K
Exp-inlet Exp-outlet Exp-sat temp
PRHR Pressure HX in-out Temp.
Primary Pressure
KAERI
Two-Phase Critical Flow with Non-Condensable Gas at High Pressure Conditions
Possible Break Points
Some possibility of SBLOCA at the top of SMART reactor
Two-phase critical flow experiments in the presence of nitrogen gas are
performed at KAERI using CFTL
ComponentCooling System
ECCS(x2)
FeedwaterLine
PRHRS(x4)Makeup System(x2)
PurificationSystem
Sampling System
Reactor Coolant System
MakeupTank
EmergencyBoronInjectionTank
ECC TankMakeupPump
Gas Cylinder
ECT
CT
PZR MCP(x4)
CEDM(x49)
IST
Purification Pump
PSVSteam Line
ChemicalAddition Tank
MC
PS
/GPZR
CORE
V1 V2MSIV
MFIV
KAERI
Critical Flow Test Loop ( CFTL )
P
L
PT
T
L
T
T
T PT
T
T
T
T
T
T
T
T
T T
P
P
PP
P
P
P
P
Line Cooler
Pump
Mixing Tank
Supression Tank
Trace Heater
Gas Heater
Air Compressor
Air ReceiveTanK
GasBooster
Flowmeter
Flowmeter
Flowmeter QuickOpening
Valve
1"
4"
8"
4"
4" 1"1"
1-1/2"
1"3/4"
1"1"
1/2"
2"
2"
1"
1/2"
1/2"
1/2"
1/2"1"
1-1/2"
1/2"
1"
Flow ControlValve System
FlowmeterGas Mixer
Steam Dump/Vent
Water In
Water In
SamplingDump
Steam Dump
Water In
Dump
Dump
N2 Gas In
T/C Sp
ool
Level
Gaug
e
N2 GasSupplyTank
Pressure ControlValve System
N2 GasInjection
Tank
PressureVessel
MainHeater
Test Section
-Short pipe (20 mm ID, 300 mm length) at sub-cooled & saturated conditions
-Small-diameter pipe (11 mm ID, 1000 mm length) at sub-cooled & saturated conditions
KAERI
Critical Flow Rate - Correlation
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.00.3
0.4
0.5
0.6
0.7
0.8
0.9
1.0
R (
=Gc/
Gc0
)
Qa/Qc0
4.0 MPa, saturated 4.0 MPa, 20K subcooled 4.0 MPa, 50K subcooled 4.0 MPa, normal temp. 7.0 MPa, saturated 7.0 MPa, 20K subcooled 7.0 MPa, 50K subcooled 7.0 MPa, normal temp. 10.0 MPa, saturated 10.0 MPa, 20K subcooled 10.0 MPa, 50K subcooled 10.0 MPa, normal temp. The Presnet Correlation
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.00.0
0.1
0.2
0.3
0.4
0.5
0.6
0.7
0.8
0.9
1.0
R = 0.378 + 0.600*e-(Qa/Qc0)/0.195
standard deviation = 7.05%
-10 %
Theo
retic
al R
(Gc/
Gc0
)
Experimental R (Gc/Gc0)
+10 %
An empirical correlation is developed as follows:195.0/)/(
22600.0378.0/ watern QQ
watern eGG −⋅+=Applicable ranges:
Pressure Range: 3.7 ~ 10.5 (Mpa)Water Temperature: sub-cooling to saturated conditionNon Condensable Gas flow rate: 0.008 ~ 0.22 (kg/s)
The standard deviation of the predictions of the present empirical correlation from the experimental values is 7.1 %.
Qn2/Qwater
watern GGR /2≡
watern GGR /2≡
KAERI
Water CHF Test
TestSection
Steam/WaterSeparator
Preheater( 40 kW )
Condenser
Pressurizer( 40 kW )
Heat Exchanger
CoolingWater
MixerDe-Ionizer
Feed PumpCirulation Pump
FlowMeter
StorageTank
Strainer
Technical Data- Max. press. and temp.: 16 MPa and 347 oC- Flow rate: 3 kg/s- Test section power: 450 kW DC, 970 kW AC - Working fluid: De-ionized water
9.52 12.6
R3 R2 R1
R6 R5 R4
R9 R8 R7
39.8
39.8
KAERI
Freon CHF Test
DC 60 Volts, 12000 Amp.Test section
TC
2000 (
Heate
d s
ection)
511
Sg.
250
325
P TC
P TC
0.934 0.925 0.928 0.926 0.933
0.931 1.118 1.114 1.113 0.932
0.932 1.127 1.130 1.120 0.933
0.933 1.123 1.124 1.122 0.928
0.933 0.929 0.930 0.934 0.930
1
2
3
4
215
6
7
8
9
10
3 4 5 66
67 68 69 610 611 612
614613 615 616 617 618
619 620 621 622 623 624
625 626 627 628 629 630
631 632 633 634 635636
31
32
36 33
35 34
40 37
39 38
44 41
43 42
11
12
29
30
64 61
63 62
68 65
67 66
48 45
43 46
13
14
27
28
60 57
59 58
56 53
55 54
52 49
51 50
15
16
25
26
23
24
21
22
19
20
17
18
KAERI
CHF Correlation
( )( )
1
2 3
"
"
inCHF
inAPS
local
A Fq
zC F F F
q z
χχ χ
⋅ −=
−⎡ ⎤⎣ ⎦⋅ ⋅ + ⋅
( )( )
" Critical heat flux" Local heat flux
z Local thermodynamic quality (calculated by MATRA-SR code)
CHF
local
qq z
χ
=
=
=
0
1000
2000
3000
4000
0 1000 2000 3000 4000
Measured CHF (kW/sq-m)
Pre
dic
ted C
HF (
kW/s
q-m
)
Mean M/P = 1.003Std. Dev. = 0.079No. of data = 372 (water)
SSF-2 correlation
KAERI
Tests
High Temperature and High
Pressure Test
Heat Transfer test for
Pressurizer
Material Corrosion Test
Steam pneumatic control valve Measurement of
steam flow rate
Surge tank
Data acquisition
system
Test section
Drainer
Circulator bath
0 50 100 150 200 250 300 350 4000
30
60
90
120
150
Wei
ght G
ain,
mg/
dm2
Exposure time (day)
Zry-4 A Zr-1Nb K2 K6
Pre-oxide처리
Zr-1Nb K2 Zry-4 A
Material Corrosion Test
High Temperature and High Pressure Test
Design Verification Tests
Heat Transfer test for Pressurizer
KAERI
Major Components Development
Steam Generator
CEDM
Main Coolant Pump MCP Performance Test
CEDM Performance Test
KAERI
Summary
SMART is a safety enhanced, economically viable and environmental friendly nuclear power plant for power generation and seawater desalination.
The SMART system adopted commercial reactor design technologies as well as innovative designs and inherent safety features.
SMART verification tests including comprehensive experiments was conducted to demonstrate overall performance of the SMART system.
Advanced design features implemented into the SMART system has been proven through various tests and experiments.