system computer code

system computer codesystem computer code

1717thth SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety

September 24-29,September 24-29, 2002007 Yalta, Crimea, Ukraine7 Yalta, Crimea, Ukraine

Development status and Development status and

ALEXANDROV RESEARCH INSTITUTE OF TECHNOLOGYSOSNOVY BOR, LENINGRAD REGION, RUSSIA

applications of the

Yu.A. Migrov, Yu.V. Yudov

Life extension and improvement of operating NPP units

Current importance of domestic Current importance of domestic best estimate computer code best estimate computer code

developmentdevelopment

Current importance of domestic Current importance of domestic best estimate computer code best estimate computer code

developmentdevelopment

17th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007 Yalta, Crimea, Ukraine


Development of the new generation NPP

designs with passive safety systems

Construction of Russian-designed

NPPs abroad

2

Two-fluid model of the system thermal hydraulics

Point model of the reactor kinetics

Accounting for liquid absorber

Models for the reactor control system components

Design schedule1996-2001

KORSAR/V1KORSAR/V1

KORSAR/V2KORSAR/V2

KORSAR/V3KORSAR/V3



Supplementary features to KORSAR /V1Supplementary features to KORSAR /V1

Spatial model of the reactor kinetics

Supplementary feature to KORSAR /V1, KORSAR /V2Supplementary feature to KORSAR /V1, KORSAR /V2

Accounting for non-condensable gases

Models for the equipment components of the reactor heat exchange loops

The main characteristics and The main characteristics and design schedule of the design schedule of the

basis versionsbasis versions

The main characteristics and The main characteristics and design schedule of the design schedule of the

basis versionsbasis versions

Models of the STU equipment components



CLOSING RELATIONS

CLOSING RELATIONS

WATER AND

STEAM PROPERTIES

WATER AND

STEAM PROPERTIES

SUPPORT PROGRAM MODULESSUPPORT PROGRAM MODULES

SYSTEM THERMOHYDRAULICS

MODULE

SYSTEM THERMOHYDRAULICS

MODULE

SPECIALIZED PROGRAM MODULES

Functional modulesFunctional modulesFunctional modulesFunctional modules



DEVELOPED AND INTRODUCED INTO SERVICE IN 1998DEVELOPED AND INTRODUCED INTO SERVICE IN 1998

CentrifugalCentrifugal pump pump

CentrifugalCentrifugal pump pump

Pressurized Pressurized steam-water steam-water

vesselvessel

Pressurized Pressurized steam-water steam-water

vesselvesselAccumulatorAccumulatorAccumulatorAccumulator

Free-level Free-level tanktank

Free-level Free-level tanktank ValvesValvesValvesValves

Reactor Reactor neutron neutron kineticskinetics

Reactor Reactor neutron neutron kineticskinetics

Heat Heat transfer transfer

structuresstructures

Heat Heat transfer transfer

structuresstructures

I versionSet of specialized

modulesSet of specialized

modules



Two-phase flow patterns in horizontal tubes

Two-phase flow patterns in horizontal tubes

- closing relations are taken from the published data

- original technique for calculating closing relations

Interfacial heat transferInterfacial shear stress



bubbly slug

dispersed

Drop-annular

stratified

StB B-St SB ADS SAD1

D2

D

F

Fcr2

Fcr2

bubbly slug

dispersed

Drop-annular

stratified

StB B-St SB ADS SAD1

D2

D

F

Fcr2

Fcr2

Characteristics of verification

procedure

Characteristics of verification

procedureVerification activities were co-ordinated by Minatom OCRKVerification activities were co-ordinated by Minatom OCRK

Participation in verification activity of specialists from other Minatom organizations (beside NITI), RAS institutes, and universities

Participation in verification activity of specialists from other Minatom organizations (beside NITI), RAS institutes, and universitiesMaking the most use of Russian Standard Safety ProblemsMaking the most use of Russian Standard Safety Problems

Making use of ISP available in RussiaMaking use of ISP available in RussiaWide use of cross verifications Wide use of cross verifications



7

LIST of integral LBLOCA and SBLOCA simulation experiments for VVER

LIST of integral LBLOCA and SBLOCA simulation experiments for VVER

Test facility Experiment type Experiment name

SBSB LBLOCA SB/1

PSB-VVERPSB-VVER

LBLOCA GT-2x25-02

SBLOCA VKS-4.0-02

SBLOCA GZ-1.0-02

SBLOCA PV-1.3-05

SBLOCA PP-26-03

SBLOCA XT-2.4-05

SBLOCA XT-3.0-02

SBLOCA XT-11-05

SBLOCA XT-16-01

SBLOCA UP-11-07

ISB-VVERISB-VVER

SBLOCA SPB-1

SBLOCA SPB-2

SBLOCA SPB-3

IST(EC)IST(EC) NC NC-05/12-95/11

KEDRKEDRNC KE-1

NC KE-2

PMK-NVHPMK-NVH

SBLOCA SPE-1

SBLOCA SPE-2

SBLOCA SPE-4

PACTELPACTEL NC ISP-33

BETHSYBETHSYSBLOCA ISP-27

SBLOCA ISP-388

ISP33 ISP33

0 2000 4000 6000 8000

0

2

4

6

8

10

Pressure, МPа

0 2000 4000 6000 8000

0

10

20

30

40

Collapsed level in Pressurizer, kPа

0 2000 4000 6000 8000

0

4

8

12

16

20

Pressure drop in HL of Loop 1,kPа

0 2000 4000 6000 8000

0

20

40

60

80

100

Pressure drops in Reactor Model , kPа

- 2

0

2

4

6

0 2 0 0 0 4 0 0 0 6 0 0 0 8 0 0 0

Coolant flow rate in Downcomer, кg/s

0 2000 4000 6000 8000

-4

0

4

8

12

16

Pressure drop in HL of Loop 2,kPа

Experiment Calculation

Integral system verification at the PACTEL test facility

Integral system verification at the PACTEL test facility



9

SAPFIRSAPFIR--KORSARKORSAR NeutronicsNeutronics – – Thermal-HThermal-Hydraulics ydraulics CalculationCalculation

SAPFIR SAPFIR KORSAR/V2 KORSAR/V2

RC RC КАRТА КАRТА

Software configurationSoftware configuration



10

Parameter DYN3D BIPR-8 HEXTRAN KORSAR

KK00effeff 0,9999410,999941 0,9984420,998442 0,9990200,999020 0,9986900,998690

KK11effeff 1,0097921,009792 1,0086731,008673 1,0091811,009181 1,0089141,008914

,%,% 0,97550,9755 1,01431,0143 1,00691,0069 1,01471,0147

3,983,98 3,223,22 4,024,02100%1Δρ

Δρ

DYN3D

0 0.1 0.2 0.3 0.4 0.5В р емя , с

0

40000

80000

120000

Мощ

ност

ь, М

Вт

HEXTRAN

DYN3D

BIPR8

КОРСАР

В то р ая к и н ети ч еск аяза д а ч а (A E R -2)

И зм ен ен и е н ей тр о н н о й м о щ н о стиAER-2

Po

we

r, M

W

Neutron power

Time, s

KORSAR

AER-2. Results of static calculation



11

7878

77

106106

1049393

92

9595

95103103

1029796

94

109109

1119696

96110110

1089796

94

9898

100113113

1139696

96103103

1029493

92

114115

1169898

100109109

1119595

95106106

1047878

77

111111

1149797

100110110

1139898

99108108

1099494

94102102

101

SAPFIR_97 & RC

EXPERIMENT

BIPR

Relative Power Distribution in Fuel Assemblies (Rostov-1 NPP)

Т=196.5 eff. day



12

ATWS with RCP coastdownATWS with RCP coastdown

NORD NPP (Germany)

0 40 80 120 160 200

252

256

260

264

268

272

Experiment, loop 1Experiment, loop 5

Coolant temperature in cold legs of loops with RCP in operation

0 10 20 30 40

1.84

1.88

1.92

1.96

2

2.04

2.08

Position of control rods

Dis

tan

ce

fr o

m c

or e

bo

tto

m,m

.

0 40 80 120 160 200

0

0.4

0.8

1.2

Revolutions of RCP-3 in coastdown mode

Re

vo

luti

on

s,

r .u

.

Te

mp

era

t ure

, C.

1.02

0 10 20 30 40

0.99

1

1.01

Relative neutron power of core

Po

we

r, r

.u.

KORSARTRAPExperiment



13

The number of components – 4 (N2, H2, O2, He) The number of components – 4 (N2, H2, O2, He) Carry-over in the liquid and gas phases Carry-over in the liquid and gas phases Thermal and mechanical equilibrium of NG components and

carrier phases

Thermal and mechanical equilibrium of NG components and carrier phases

NG effect on mass and energy balance of the liquid phase is not accounted for

NG effect on mass and energy balance of the liquid phase is not accounted for

Effect of non-condensing gases on heat transfer Effect of non-condensing gases on heat transfer

gas release from liquid phase gas release from liquid phase

radiolysis of the coolant components radiolysis of the coolant components

ingress from external sources ingress from external sources

metal-steam reaction metal-steam reaction

NG sources: NG sources:

Characteristics of modeling Characteristics of modeling

non-condensing gas (NG) non-condensing gas (NG) behaviorbehavior

Characteristics of modeling Characteristics of modeling

non-condensing gas (NG) non-condensing gas (NG) behaviorbehavior



14

Verification of the model against experiments of

Kuhn et al.

Verification of the model against experiments of

Kuhn et al.

Temperature distribution along the channel lengthTemperature distribution along the channel length

experiment, Wcalculation, Werror,%

2-1- 5 0.059 27958 26852 - 4

1-1- 3R 0 33473 34003 + 1.6

Run Air mass Total heat fraction flux Δ%

2-1- 8R 0.148 21270 24607 +15.72-1-13 0.396 17640 19948 +13.1

0 0.5 1 1.5 2 2.5340

360

380

400

420

Ti

Ts,v

Tw

Te

mp

era

ture

, K

Z,m



15

17th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007 Yalta,

Crimea, Ukraine17th SYMPOSIUM of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007 Yalta,

Crimea, Ukraine16

0 0.2 0.4 0.6 0.8 1О тн о си тел ь н о е п ар ц и ал ьн о е д авл ен и е га за (а зо та )

0

5000

10000

15000

20000

25000

Мощ

ност

ь, В

т

эксперимент расчет

Э ф ф ек ти в н о сть теп л о п ер ед ач и в П Гп р и д авл ен и и 0 .2 М П а

С т ен д Л -1 0 7 0О т р а в л ен и е П Г

0 0.2 0.4 0.6 0.8 1О тн о си тел ьн о е п ар ц и альн о е д авл ен и е газа (а зо та )

0

10000

20000

30000

Мощ

ност

ь, В

т



С тен д Л -1 07 0О тр а в л ен и е П Г

0 0.2 0.4 0.6 0.8 1О тн о си те л ь н о е п ар ц и ал ьн о е д авл ен и е га за (а зо та )

0

10000

20000

30000

40000

Мощ

ност

ь, В

т



С т ен д Л -1 0 7 0О т р а в л ен и е П Г

Po

we

r, M

W

Po

we

r, M

W

Po

we

r, M

W

L-1070

Test facility SG

L-1070

Test facility SG

Test facility SG

L-1070

P= 0.2 MPa

P= 2.0 MPa

P= 0.5 MPa

Relative partial pressure of gas



experimentcalculation calculation

calculation

experiment

experiment

Verification of the model against

experiments of Cairns and Roper Verification of the model against

experiments of Cairns and Roper

Parameters of experimentsP = 105 Pa 0.8 ≤ Gg ≤ 3.4 kg/s 0.25 ≤ Xa ≤ 1 370 ≤ Tgin ≤ 705 K3 ≤ Gf ≤ 20 gm/s 305 ≤ Tf ≤ 370 K (d = 22.9 mm l = 0.946 m)

0 60 120 180 240Steam-air flow temperature head, 0K

(experiment)

0

60

120

180

240

Ste

am-a

ir f

low

te

mp

erat

ure

hea

d, 0 K

(cal

cula

tio

n)

+ 11%

0 0.05 0.1 0.15 0.2 0.25Evaporation mass flux10

3, kg/c

(experiment)

0

0.05

0.1

0.15

0.2

0.25

Ev

ap

ora

tio

n m

as

s f

lux

x1

03

, kg

/c(c

alc

ula

tio

n)

+ 20 %



17

The KORSAR system code is a new generation software tool designed for computer-based analysis of VVER dynamics. It is characterized by enhanced versatility, high level of physical-mathematical models, user-code friendly interface, and flexible topology.

The KORSAR system code is a new generation software tool designed for computer-based analysis of VVER dynamics. It is characterized by enhanced versatility, high level of physical-mathematical models, user-code friendly interface, and flexible topology.

The first base version KORSAR /V1.1 has been certified at Gosatomnadzor (2003) and put in trial run at OKB “Gidropress”, SPbAEP and is now used in design calculations for VVER safety analyses.

The first base version KORSAR /V1.1 has been certified at Gosatomnadzor (2003) and put in trial run at OKB “Gidropress”, SPbAEP and is now used in design calculations for VVER safety analyses.

The completion of the second and third base versions development and verification will much extend the KORSAR code application area for the VVER NPP safety analysis purposes.

The completion of the second and third base versions development and verification will much extend the KORSAR code application area for the VVER NPP safety analysis purposes.

ConclusionsConclusions ConclusionsConclusions



18

system computer code

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