NE in Croatia: ResearchNE in Croatia: Research, Operation, and Regulation

Zdenko SimicUniversity of Zagreb,

Faculty of EE and Computing, CroatiaNPEC Meeting July 27, 2011.

C SDana Point, CA, USA

2

Croatia ‐ Basic Facts (2009)Croatia Basic Facts (2009)Plitvice Total area: 88 kkm2

kk l dAdriatic sea

(55 kkm2 land)

Total population: ~ 4.5 Mp p 4 5

GDP : 45G€, 10 k€/per capita

Dubrovnik Installed el. capacity:  4 GWe

Elec  consum :  17 7TWh Elec. consum.:  17,7TWh

NPP Krško produces ~5 TWh

3

Zagrebp

(Slovenia & Croatia)

NE Related Research at Faculty of ElectricalFaculty of Electrical

Engineering and Computing

(tnx. to Davor Grgić)( g )

NE related research @FERNE related research @FER

• Thermal-hydraulics safety analysesThermal hydraulics safety analyses– IRIS, SPES-3, coupled codes

Probabilistic safety assessments• Probabilistic safety assessments• Core design and fuel management• Emergency planning – Technical support• Severe accident analysisSe e e acc de t a a ys s

5

Thermal-hydraulics safety analysesThermal hydraulics safety analyses

• Experience since 1984p– Almost all Chapter 15 calculations performed for NPP

KrskoDeveloped and maintained NPP Krsko nodalization– Developed and maintained NPP Krsko nodalizationfor RELAP5, user training and qualification

– Developed containment nodalization for GOTHIC code

– Support for NPP Krsko full scope simulator verification

– Recalculation of plant transients– Analytical support for equipment/procedures

modification6

modification– Support in AOP/EOP verification

NPP Krsko nodalization

469 volumes497 junctions376 heat structures

7

575 control vars402 trips

NPP Krsko EQ project

• Equipment selectionEquipment selection• Calculation of thermal-hydraulics and radiation

tparameters• Source-term calculation• Development of EQ zones for RB, AB and IB rooms• Database with EQ data• Database with EQ data• Codes used: RELAP, GOTHIC, ORIGEN,

8

ELISA, QAD, DIDOS

IRIS activitiesIRIS activities

• Member since year 2000• Responsibility for safety analyses

coordination– Development and maintenance of plant

nodalization– Coupled R5G SBLOCA calculation

• Support in preparation of SPES-3 testingSuppo p epa a o o S S 3 es g• Neutronics calculations/elements of core

design9

design

SPES3 RELAP5 containment nodalization

Environment12

1

Dry well (subdivided, 64 volumes)Volume = x m3

Elevation = x mHeight = x mHydralic diameter = x mInitial temperature = 48.9 oCLiquid pressure = 101.325 kPaRH = 0%Liquid fraction = 0%

LGMS tanks (total for 2 tanks)Volume = x (water x/gas x) m3

Elevation = x mHeight = x mHydralic diameter = x m

PSS-LGMS conecting pipes (total for 2 pipes)Volume = x m3

Elevation = x mHeight = x mHydralic diameter = x mInitial temperature = 48.9 oCLiquid pressure = 101.325 kPaRH = 0%Liquid fraction = 0%

ADS Quench TankVolume=x m3

El ti0.4431

0.5529

0.6667

0.7765

0.8863

1.000

14 15

1F 2F

75

10 118 9

8 3 13

4 9

5F

16

Initial temperature = 48.9 oCLiquid pressure = 107.2 kPa (COV)RH = 0%Liquid fraction = 66.7%

ADS el x m

DVI/LGMS connection el x m

21

2215

7

23

16

12

24

1727

Elevation=x mHeight=x mHydraulic diameter=x mInitial temperature = 48.9 oCLiquid pressure = 113.9 kPaRH = 0%Liquid fraction = 93.8%

0.1000E-09

0.1098

0.2196

0.3333

0.4431

1

9 10

7 8

16

10

3

1F 2F

6F/7F17/18

2

5 10

6 11

PSS tanks (total for 2 tanks)Volume = x m3 (water/air x/x m3)Elevation = x mHeight = x m (x-x m, x-x m)Hydralic diameter = x/x mInitial temperature = 48.9 oCLiquid pressure = 112.36 kPaRH = 0%Liquid fraction = 85.7/0.0% (el x m)

PSS tanks vents (total for 2 vents)Volume = x/x m3

Elevation = x-x m/x-x mHeight = x/x mHydralic diameter = x/x mInitial temperature = 48.9 oCLiquid pressure = 101.325 kPaRH = 0%Liquid fraction = 26.2/0% (el x m)

2 “Break el x m

RV cavityVolume = x m3

Elevation = 0 mHeight = x mHydralic diameter = x mInitial temperature = 48.9 oCLiquid pressure = 101.325 kPaRH = 0%Liquid fraction = 0%

4 619 20

13 14

3F/4F 14/15

CAVel x m

2 3 5

12 13

4 6

Time= 2000.000 s

Code development• Coupled codes (th sys+neut th sys+cont )

INPUT

• Coupled codes (th.sys+neut., th.sys+cont.)• Fuel assembly transport code for

neutron cross section calculation

Resonance calc.

Micro XS

Resonance calculation –

• Development of advanced PSA toolsand integration of on-line monitoringapplications

Dancoff factorSelf-shielding correction

Macro XS

applications XS condenzationRay tracing and CP matrix

generationEigenvalue calculation

Flux expansion

eple

tion

step

Fundamental mode calc.B1 critical buckling search

EDIT

Burnup calculation

De

21.505

UO fuel rod2

0.95

2

0.824

Burnup calculationPredictor-corrector

Next stepTRUE

1.265

0

Gd bearingfuel rod

1.265

0.95

2

0.824

11EXIT

FALSE1.140

RCC guidethimble orinstr. thimble1.

220

1.265

Coupled code calculationCoupled code calculation

2 0E+09

2.2E+09

nek21e00 runid:mslb 3d

5 5

6

N EK CY C21 MSL B , EOL , A =0.030 m2

nominal 32 5 psia

ower

(W

)

1 0E 09

1.2E+09

1.4E+09

1.6E+09

1.8E+09

2.0E+09

0.031 m2 0.030 m2 0.029 m2 0.028 m2 0.026 m2 0.025 m2 R ca

l DN

BR

3.5

4

4.5

5

5.5 -32.5 psia +3.6 F -5% flow +10% power all

Po

2.0E+08

4.0E+08

6.0E+08

8.0E+08

1.0E+09 0.024 m2 0.023 m2 0.022 m2 0.021 m2

R5PLOT FER v1.4 14:56:12, 10/10/200

Loc

1.5

2

2.5

3

PLOT FER V1W

21:43:00, 25/12/0

0 20 40 60 80 100 120 140 160 180 200T IME (sec)

0

05

0 2 4 6 8 10 12 14 16 18 20 22 24A xial l ayer [ ]

1

05

900

1000

1100

1200

1300

12600

700

800

X axis

Y axis

ax pos 1

On-line Risk Monitoring

13

Probabilistic Safety Assessment (PSA)• Level 1 i Level 2 support• On-Line Risk Monitoring

y ( )

g• NEK PSA Supporting Analysis Calculations• Modeling CCF Groups in NEK PSA Model• Auxiliary Tool for Level 2 Quantification• ESW/CCW Fault Tree Model Enhancements• Other External Events Analysis Update• Other External Events Analysis Update• NEK LPSA Event Tree Notebook• Update of System Failure Probabilities for NEKUpdate of System Failure Probabilities for NEK

Shutdown Safety Analysis• Codes (PSA, On-Line RM):

14

( , )• RiskSpectrum, RiskMan, CAFTA, RiskWatcher, …

Core design and fuel managementCore design and fuel management

• Generation of XS dataGeneration of XS data• 3D nodal depletion

C li it d RSAC t l l ti• Core limits and RSAC type calculation• In-core fuel management

15

Core Calculations

2.2

1.269

1.710

6.81

1.21.41.61.82

2.2

PP Recon2 -1.318

-0.8767

-0.4506

-0.2459E-01

0.4167

0.8427

20 40 60 80 100

2040

6080

100120

.2

.4

.6

XY axis

0

5-1-.5

0.51

1.5

-2.170

-1.744100 120

120X axisBU=

16

05

10

5

10-2

-1.5

X ax is

Y a

xis

ax pos 1

Emergency Planning – Technical SupportEmergency Planning Technical Support

17

Authorized institution for safety reviewsAuthorized institution for safety reviews

• Croatian State Office for Nuclear SafetyCroatian State Office for Nuclear Safety• Slovenian Nuclear Safety Adminstration• Activities:• Activities:

– NEK TMI action plan– FSAR/USAR conversion– Safe Shutdown Assessment– NPP Krsko modernization – Software services

Si l t ifi ti– Simulator verification– PSR issues resolution– Modification reviews

18

Modification reviews

International cooperationInternational cooperation

– NRC, IAEA, OECD/CSNI , ,• International Benchmarks

– University of Pisa, GRS • SUNCOP, uncertainty, user effects, scaling,

experimental facilitiesPOLIMI (IRIS CFD)– POLIMI (IRIS, CFD)

– ISS (SCDAP Development and Training Program), Regional Training Centreg ), g g

– Westinghouse (IRIS, NPP Krsko)– Framatome ANP (PSA CCF)

19

( )

Severe accident analysesSevere accident analyses

• Started in 2001Started in 2001.• Participation in OECD/CSNI ISPs and

BenchmarksBenchmarks– QUENCH and PHEBUS FPT experiments

lid ti f RELAP5/SCDAP d• validation of RELAP5/SCDAP code

• Application of SA codes to NPPs• Recently, usage of MAAP code• Initial usage of ASTEC code

20

g

Comparison of SCDAP/RELAP5 and MAAP results

7

Smaller break, RELAP and MAAP comparison

350

Smaller break, RELAP and MAAP comparison

RELAP MAAPTop of the core

ater

leve

l (m

)

4

5

6

RELAP MAAP

hydr

ogen

(kg)

200

250

300 MAAP

Bottom of the core

Col

laps

ed w

a

1

2

3

Acc

umul

ated

h

5010

015

000

Larger break, RELAP and MAAP comparison

0 3000 6000 9000 12000 15000Time (s) 0 3000 6000 9000 12000 15000

Time (s)

7

Larger break, RELAP and MAAP comparison

ogen

(kg)

200

250

30

RELAP MAAP

Top of the core

er le

vel (

m)

4

5

6

7

RELAP MAAP

Acc

umul

ated

hyd

ro

100

150

Bottom of the core

Col

laps

ed w

ate

1

2

3

4

0 3000 6000 9000 12000 15000Time (s)

A

50

21

0 3000 6000 9000 12000 15000Time (s)

1

Nuclear Energy–Global Trends and Perspectives in South-East Europe

CROATIAN ENERGY STRATEGY AND NUCLEAR POWER PROGRAMMENUCLEAR POWER PROGRAMME

dr.sc. Kristina Čelić

Ministry of Economy, Labour and Entrepreneurship

Republic of Croatia

22

Podgorica, Montenegro, 10-12 May 2011

BASIC CROATIAN ENERGY STRATEGY OBJECTIVES

National Energy Strategy is adopted by the Croatian Parliament on October, 16th 2009.

The Croatian Energy Strategy has three basic energy objectives:— Security of energy supply;— Competitiveness of energy sector;

S t i bl d l t— Sustainable development.

23

3 SCENARIOS AND CO2 EMISSIONS

40,0

45,0

50,0

Blue scenariowithout NPP (gas,

l RES)Kyoto targetBase year

25,0

30,0

35,0

CO

2eq

coal, RES);NPP after 2020 in

Green (gas, NPP, RES) d Whit

10,0

15,0

20,0

1000

ktC RES) and White

scenario (gas, coal, NPP, RES);

Aft 2020 CCS0,0

5,0

1990 1995 2000 2005 2010 2015 2020 2025 2030

After 2020 CCS technology included.

Emission 1990.-2005. 'Blue'' scenario 'Green'' scenario

'White'' scenario Kyoto target Base year

Even with nuclear option Croatia will have difficulties meeting binding targets for CO reduction until 2020 while maintaining security of supply

24

targets for CO2 reduction until 2020 while maintaining security of supply and competitiveness.

NUCLEAR - PRESENT NATIONAL POSITION

National Energy Strategy is adopted by the Croatian Parliament on October, 16th 2009 decided in favour of launching the Croatian Nuclear Energy Program (CRONEP), consistent with the IAEA methodology.

Before making the decisions on building the nuclear power Before making the decisions on building the nuclear power plant, it is necessary to perform preparation activities in accordance with the International Atomic Energy Agency (IAEA). ( )

Decision on the construction of a nuclear power plant will be taken by the Croatian Parliament.

Plan is to decide on building the nuclear power plant by 2012 -not realistic but launching nuclear program has potentials and is in the process.

25

EXPERIENCE IN NUCLEAR

The Republic of Croatia has previous nuclearexperience and belongs to a group of countries that use nuclear power for energy purposes.p gy p p

Hrvatska Elektroprivreda (Croatian Power Utility) is co-owner of 700 MW NPP Krško in Slovenia.

Croatian nuclear experience arises from:— more than 10 years of preparations and construction of NPP

Krško;;— 28 years of successful operation of NPP Krško;— preparation for construction of the first NPP in Croatia carried

out until 1987 (NPP Prevlaka).

Positive influence of NPP Krško construction and operation is still present in the Croatian industry.

26

In 1987 NPP Prevlaka project was terminated afterChernobyl accident.

ROLE OF CRONEP

The launching of the Croatian Nuclear Energy Programme comprises two basic goals: — providing for existence (co-existence) in immediate

vicinity of two nuclear power plants and five nuclear reactors in NPP Krško and NPP Paksreactors in NPP Krško and NPP Paks

— providing for preconditions required for decision making and realization of nuclear power plant construction.

Nuclear safety and public awareness will be in the focus of the CRONEP.

27

REPUBLIC OF CROATIASTATE OFFICE FOR RADIOLOGICAL AND NUCLEAR SAFETY

LICENSING PROCESS FOR NUCLEAR INSTALLATIONS IN THE REPUBLIC OF CROATIA

Saša Medaković, State Office for Radiological and Nuclear Safetyg y

28

National Nuclear Infrastructure29

Strategic Documents:- Energy Development Strategy (2010-2020)

Strategy implementation program (in preparation)- Strategy implementation program (in preparation)- Act on Radiological and Nuclear Safety (OG 28/2010)- Nuclear Energy Act (not exist)Nuclear Energy Act (not exist)- Strategic decision by Parliament (not later then 2012)

REPUBLIC OF CROATIASTATE OFFICE FOR RADIOLOGICAL AND NUCLEAR SAFETY

Updates since Publication of 2008 National Report

30

National Report

Early warningt dsystem upgrade

(2010) RODOS systemy

instalation (2009)

REPUBLIC OF CROATIASTATE OFFICE FOR RADIOLOGICAL AND NUCLEAR SAFETY

Plans for Nuclear Power Introduction31

New Energy Strategy

D i i f

Bidding process

Decision for1st NPP Commissioning

1st Croatian NPP Project1st Croatian NPP Project

16 October 200916 October 2009 Not later Not later th 2012th 2012

201x (?)201x (?)202x (?)202x (?)

REPUBLIC OF CROATIASTATE OFFICE FOR RADIOLOGICAL AND NUCLEAR SAFETY

then 2012then 2012 202x (?)202x (?)EstimationEstimation

Based on the StrategyBased on the Strategy

Thank you for your attention!y f y

9th International Conference on NuclearOption9 pin Countries with Small and MediumGrids

2012  June 3‐6  Zadar  Croatia2012, June 3 6, Zadar, CroatiaCroatian Nuclear Society

Zada

zdenko.simic@fer.hrZadar