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April 18 2007 April 18 2007 Si Si - - Hwan Kim Hwan Kim Verification Tests performed for Development of an Integral Type Reactor

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Page 1: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

April 18 2007April 18 2007

SiSi--Hwan KimHwan Kim

Verification Tests performed for Development of an Integral Type Reactor

Page 2: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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

Page 3: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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

Page 4: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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

Page 5: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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

Page 6: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

KAERI

SMART vs. VISTA Design

Steam Generator

ReactorVessel

Pressurizer

GasCylinder

MCP

SG

Core

CEDM

PZR

Shielding

MCP

ReactorVessel

••Scale LawScale Law

Page 7: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

KAERI

VISTA Facility

Page 8: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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

Page 9: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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

Page 10: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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

Page 11: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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

Page 12: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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

Page 13: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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

Page 14: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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≡

Page 15: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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

Page 16: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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

Page 17: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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

Page 18: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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

Page 19: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

KAERI

Major Components Development

Steam Generator

CEDM

Main Coolant Pump MCP Performance Test

CEDM Performance Test

Page 20: Verification Tests performed for Development of an Integral Type … · 2007. 6. 12. · 9Database for design optimization of SMART reactor and code validation VISTA : Experimental

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.