PKL III Test Facility - nrc.gov · PKL Presentation June 2003.ppt - 06-2003 - R-904748 - FANP...

PKL Presentation June 2003.ppt - 06-2003 - R-904748 - FANP TGT1/Um

PKL III Test Facility

Integral test facility simulating a 1300 MW PWR

• 4-Loop configuration

• All relevant safety and operational systems on the primary and secondary side without turbines and condensers

• Volume and power scale 1:145

• Elevations 1:1

Objectives

• Thermal hydraulic system behavior under accident situations

• Verification and Optimization of cool-down procedures

• Database for the validation of computer codes

• Demonstration of safety margins

• Resolution of safety issues of current interest

• Training of the operating staff


PKL III Boron Concentration Measurements

x

COMBO

x x

HP- / LP-Injection

Loop 1}Loop 1

Fluid temperature

Wall temperature

Combi. Temp. Sensor

Grab sampling

CL 1+2

Loop 1

Loop 1-3

Loop 1COMBO

Loop 1-3

Continuous Measurement of

Boron Concentration (COMBO)

Counter Tubes Neutron source

Coolant to bemeasured Pipe


PKL-Tests Concerning Boron Dilution

Background:

� Low borated water entering the core can lead to local recriticality and

thereby to a power excursion

� A necessary condition for this to happen is the formation of low borated water slugs in the primary and their transport to the core without sufficient mixing

� Formation of low borated water slugs might occur by separation of borated

and almost boron free coolant within the primary, e.g. by

→ Small Break and Reflux-Condenser Conditions

→ Loss of RHRS under shut-down conditions followed by steam production in the core and condensation in the SG


� Break in the hot leg of the pressurizer loop(40cm2)

� 100 K/h cooldown of the SG-secondaries

� HP-SIP: into all 4 loops- E1.1 cold leg- E2.1 hot leg

� Continuous boron concentration measurement (COMBO) at the RPV inlet- E1.1 in loop 1- E2.1 in all 4 loops

PKL-Tests Concerning Boron Dilution after SB-LOCA

Symmetrical injection into all 4 loops (E1.1, E2.1)

SG SG

PRZ

RPV

Borated waterSteamLow borated water

Initial conditions


PKL-Tests Concerning Boron Dilution after SB-LOCA

� Break in the cold leg of loop 1 (32cm2)

� 100 K/h cooldown of the SG-secondaries

� 2 out of 4 HP-SIPs (cold leg, 1 in break loop)

� Continuous boron concentrationmeasurement(COMBO) at the RPV inletin all 4 loops

Maximum amount of unborated water: cold leg injection (E2.2)

SG SG

PRZ

RPV

Borated waterSteamLow borated water

Initial conditions


PKL III E2.2 - Transport of Condensate Slugs due to Restart of Natural Circulation

0

1000

2000

3000

3000 3200 3400 3600 3800 4000

Bor

on c

once

ntra

tion

at R

PV in

let Boron concentration at RPV inlet in loops 1, 2, 3 and 4

[B]-curves represent floating average (20 s)

in p

pm

0

1

2Natural circulation in loops 1, 2, 3 and 4

Mas

s flo

w in

kg/

s

T ime aftertest start

in s


PKL III E3.1: Loss of RHRS

Scenario� Total failure of RHRS

when the reactor isshut down, e.g. forrefuelling (primarysystem still closed)

� 2 SGs filled with water,one of both (SG 1)ready for operation

Objectives� Takeover of residual

heat removal by theSG ready for operation

� Evolution of localboron distribution

Initial Conditions

SG 4Psec = 1.0 bar

SG 1Psec = 1.0 bar

SG 2Psec = 1.0 bar

SG 3Psec = 1.0 bar

Pprim ~ 1 barTcore, out = 60 °C

Decay heat = 0.7 %

[B] = 2200 ppm, homogeneous

RHR in operation fortest preparation -but fails at test start

Water prim., subc. > 10 KN2 primary

Water sec.Air sec.



� Failure of RHRS has lead to:

�� Core heat up and steam production

�� Increase in liquid level and primary pressure

�� Condensation in the SGs

� Heteregenous behavior inthe individual SG U-tubes:

�� Slug of subcooled water in the long U-tubes

�� Intermittend overflow of low borated condensate in the small U-tubes

Situation after 7 - 8 hours

SG 4Psec = 1.0 bar

SG 1Psec ~ 2.0 bar

SG 2Psec > pprim

SG 3Psec = 1.0 bar

Pprim = 5 barTcore, out = 150 °C

Decay heat = 0.7 %

[B] = 2200 ppm, inhomogeneous

Water prim., subc. > 10 KWater prim., subc. < 10 K

Water/steam mix. prim.N2/steam mix. prim

[B] = 800 ppm

[B] = 4400 ppm

1400 ppm

[B] = 1200 ppm

Q�

1700 ppm

COMBO[B]

m�


0

1000

2000

3000

4000

5000

-4500 0 4500 9000 13500 18000 22500 27000 31500 36000 40500 45000

Boron concentration in ppm

Time in s

COMBO in loop seal 1(continuous measurement)

Sampling at DC bottom

Sampling at core inlet

Sampling at core outlet

0

1

2

3

4

5

6

7

8Pressure in bar

Primary

SG 1 secondary

Controlling ofsec. pressurein SG 1

Begin of ACC injection

Return toRHRS

Failureof RHRS


� Primary pressure stabilizesafter about 5 h at 5 bar

� Heat transfer by steamproduction in the coreand condensation in theSG in operation

� Intermittend overflow ofcondensate (low boratedwater) to the cold side insome SG U-tubes

�Slow but continuousdecrease in boronconcentration at theSG outlet and withsome delay also inthe RPV downcomer


Application of PKL Test Results to PWR Plants

Use of the PKL Results

� Understanding of the thermal hydraulic behavior during theinvestigated accident scenarios� System behavior� Local behavior (e.g. SG tubes)

� Application on NPP operation� Contribution to the resolution of a safety issue of current interest (e.g. size

of accumulated low borated water is limited and smaller than expected,restart of NC does not occur simultaneously in several loops)

� Impact on operating procedures

� Support for Code analyses� Validation and development of TH system codes� Boundary conditions for further experimental and/or analytical

investigations on mixing in the RPV downcomer


New Program PKL - 2

> Starting in the second half of 2003

> Program period: 3 years

> 7 Experiments (partly with several test runs)


New Program PKL - 2

Proposed Topics of Investigation(priorities according to comments during 4. PRG and further feedback by the participants)

� Tests on loss of residual heat removal under shut-downconditions with closed RCS (3 Tests with 8 Test Runs)

� Tests on boron dilution after SB-LOCAs (2 Tests)

� Test on loss of residual heat removal under shut-down conditionswith open RCS (1 Test with 2 Test Runs)

� Test on boron precipitation during LB-LOCA (1 Test)

PKL III Test Facility - nrc.gov · PKL Presentation June 2003.ppt - 06-2003 - R-904748 - FANP...

Documents

Transcript of PKL III Test Facility - nrc.gov · PKL Presentation June 2003.ppt - 06-2003 - R-904748 - FANP...