1

Seventh International Scientific & Technical Conference(MNTK-2010)

Moscow, 26 – 27 May 2010

Russian Nuclear Power in the Ever-changing World

V.G. Asmolov

Beloyarsk NPP

Balakovo NPP

Novovoronezh NPP

Kursk NPP

Kalinin NPP

Kola NPP Leningrad NPP

Smolensk NPP

Bilibino NPP

Rostov NPP

VVER-1000 (10 GW – 41,3%)VVER-440 (2,6 GW - 11%)

BN-600 (0,6 GW – 2,5%)EGP-6 (0,05GW – 0,2%)

RBMR-1000 (11 GW - 45%)

2

Russian NPPs in commercial operation1010 NPPs, 3232 Units, Ninst.= 2424224242 MW

33

Electricity generation by Russian NPPs

119,6

119,2

97,8 99,3

108,8 108,3

103,5

120,0128,9

134,9

139,8148,6

143,0147,6

154,7

158,3 162,3

163,3

169,2

90

140

190

240

1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010

bln

kW-h

Volgodonsk (Rostov) NPP

Unit 1 commissioned

Balakovo NPPUnit 4

commissioned

Kalinin NPP Unit 3

commissioned

Rostov NPP Unit 2

commissioning

44

Load Factor of Russian NPPs

55

Load Factor at Russian NPPs in 2009

81,7475,59

39,94

64,1674,9976,5378,2484,27

89,3295

0

20

40

60

80

100

120

VolgodonskBalakovo

KalininSmolensk

KurskBeloyarsk

Leningrad

Novovoronezh KolaBilibino

66

100,6%109,6% 107,4%

102,4% 101,0%100,9% 100,8% 100,3% 100,2% 100,0%

88,6%

1632

78,4

8321

,9

4022

,3

3129

9,0

167,

9

2648

5,5

1204

7,2

2741

5,3

2148

1,5

2214

6,6

9891

,2

0%

20%

40%

60%

80%

100%

120%

REA

VolgodonskBeloyarsk

BalakovoBilibino

Leningrad

NovovoronezhKursk

SmolenskKalinin Kola

Execution of the planned target for electricity generation at Russian NPPs

in 2009 (% and mln. kW-h)

77

Trend of operational events at Russian NPPs

4 01 2 0 0 0 0 0 1

65 67

3745

44 4042 47

3828

6967

3847

4440 42

4738

29

0

10

20

30

40

50

60

70

80

2000 2001 2002 2003 2004 2005 2006 2007 2008 2009

Important for safety Others

88

Trend of events with scrams at Russian NPPs

12

89

12

6

1110

1315

0

2

4

6

8

10

12

14

16

2001 2002 2003 2004 2005 2006 2007 2008 2009

99

Radioactive noble gases releases from NPPs in 2009

(% of the allowed release level)

2,0

25,8 25,7 21,0 20,517,7 17,0 17,0 18,0

1,7 9,2 8,6 11,1 10,2 10,4 7,3 3,2 5,50,1 3,6 3,6 4,0 4,7 2,0

2,8 4,1 3,80,0 0,8 0,3 1,3 1,0 1,8 0,4 0,3 0,60

5

10

15

20

25

30

2001 2002 2003 2004 2005 2006 2007 2008 2009BN

RBMK

BN VVER RBMK EGP

New limits for allowed release

introduced (by SP AS-99 standard)

On-line data for 2009

1010

Collective doses at NPPs for different reactor types (man-Sv/Unit)

5,94 5,85

4,42 4,233,35 3,87

3,39 3,21 3,312,67 2,58 2,09

1,92 1,59 1,66 1,57 1,44 1,521,26 1,12 1,08 0,9 0,89 0,68 1,04 0,62 0,750,8 0,77 0,73 0,62 0,53 0,5 0,48 0,57 0,590

123456789

10

2001 2002 2003 2004 2005 2006 2007 2008 2009

RBMKs All NPPs VVERs Non-serial (EGP, AMB, BN)

1111

Summary of the year 2009

►Nuclear power units safe operation has been ensured

►The maximum electricity generation level of 163.3 bln kW-h (100.6% of the FTS balance target) has been achieved

►The maximum generation capacity of 22 700 MW has been attained

►Load Factor of 80.2% has been reached (79.5% in 2008)

►Availability Factor of 83.6% has been reached (82.2% in 2008)

1212

Production targets for 2010

Planned generation as per FTS balance target

- 169.2 bln kW-h

Load Factor

- 81,3 %

1313

Electricity generation increase at the operating nuclear power units is achieved by implementation of relevant measures in the following areas:

►Reliability improvement;►Nuclear power units efficiency factor raise;►Thermal power increase;►Reduction of overhaul and mid-life repair terms;►Thermal efficiency improvement for thermomechanical

equipment;►Operation life extension for NPP units.

Electricity generation increase

1414

The gradual comprehensive upgrading plan for VVER-1000 power units

Reactor Steam Generator Turbine Generator

►Reduction of conservatism in defining the design basis and operational limits.

►Reduction of linear power release in a fuel element by means of axial and radial profiling.

►Fuel assembly modernization.

►Upgrading the steam separation system.

►Evaluation of internal SG pressure raising feasibility.

►Evaluation of feasibility of SG replacement with a more efficient one.

►Upgrading the flow-through part and optimization of the thermal circuit.

►Enhancement of the feedwater recovery system for efficiency factor improvement purpose.

►Upgrading in order to obtain a maximum possible electric power.

►Evaluation of feasibility of the generator replacement.

1515

Reduction of conservatism in the VVER-1000 power capability

evaluation

Parameter Value at present Conservatism reduction

Measures towards conservatism

reduction

1. Kr – fuel element power

nonuniformity coeff. 1,52 1,48 Fuel load optimization

2.qтв - fuel element power

capability, KW 110 115Reduction of conservatism in the accident analysis domain

3. Fобщ(qтв ) - margin coefficient 1,17 1,11Ensuring the overall 95% probability of being within the limits

доп

As a resultthermal power can be increased by 12%

1616

Phases of Russian Nuclear Power Development in Post-Chernobyl

Period

►1992 – 2004 - the “survival” period

►2004 – 2008 - nuclear “renaissance”

►2008 – 2009 - global financial crisis

►2010 onward - end of recession period and post-crisis development

1717

Russian NPPs built in the “survival” period

1993 – Balakovo NPP Unit 4

2005 – Kalinin NPP Unit 3

2001 – Volgodonsk NPP Unit 1

1818

Foreign NPPs of the “survival” period

Tianwan NPP(China)

Bushehr NPP(Iran)

Kudankulam NPP (India)

1919

The “survival” period outcome►R&D infrastructure and the knowledge for the basis

technology (VVER and BN reactors) have been retained

►The technology and infrastructure for the construction of NPP power units, and the whole nuclear industry have been retained

►Severe accidents research programs have been carried out, and computer codes have been developed and verified

►New safety design features have been developed and tested

20

Safety database 1986 - 2005

COMPUTATIONAL TOOL

APPLICATION TO THE NUCLEAR INSTALLATIONS

Thermohydraulics - integral experimentsHydrogen (deflagration,detonation)RASPLAV, MASCAMelt - concreteinteractionThermomechanics

of fuel elements

Thermomechanics of a reactor vessel

Reactivity initiatedaccidents

RESEARCHPROGRAMS IN RUSSIAwith Western partnersinvolvement

RESEARCH PROGRAMS FACILITIES

with Russian involvement

AT WESTERN INTERNATIONAL

PROGRAMSdata bases, codes)(

Thermohydraulics CAMP, ICAP

OECD

EU, IAEA programs

NEA /EU, IAEA programs

Severe accidents CSARPNEA / OECD

-

Thermohydraulics - PMK (Hungary), PACTEL (Finland)Core damage - CORA (Germany)

BETA (Germany), ACE (USA)Filters on the containmentventing system -

Hydrogen -

ACE (USA), TYPHOON (Germany)

HDR(Germany)Melt-concrete interaction -

2121

The public request for accelerated nuclear power development

External conditions:● Non-uniform distribution of fossil fuel resources ● Increased tension at global energy market

Demonstration of developing consumer-oriented features of NPPs:● guaranteed safety● economic efficiency● closed NFC

RW & SF management fuel breeding

Boundary conditions that determined

the nuclear “renaissance”

2222

Nuclear power globalization degree

►Five countries (U.S.A., France, Japan, Russia and Germany) altogether produce 70% of nuclear-generated electricity in the world.

►Light water reactors of three types (PWR, BWR, VVER) represent 80% of global reactor fleet.

►Five countries (Russia, France, Japan, China, India) are developing fast reactor technologies in an advanced phase.

►Six companies (Rosatom, URENCO, USEC, EURODIF, CNNC, JNFL) are performing commercial-scale uranium enrichment.

►Six countries (France, United Kingdom, Russia, Japan, China, India) have nuclear fuel reprocessing capacities.

23

2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018 2019 2020

- red line separates the units with guaranteed financing- blue line designates the mandatory power unit commissioning programme

Kola, Unit 2

Kola, Unit 1

LNPP, unit 2

LNPP Unit 1

Mandatory programme

Mandatory and supplementary programmes

Installed capacity by 2020, GW 51.6 57.4 Capacity to be commissioned, GW 32.1 38.9

Kola-IIUnit 1

Kola-IIUnit 2

Cen

tral

, U

nit 1

Kola-II, Unit 3

Kola-II, Unit 4

Prim., Unit 1

Prim., Unit 2

To be decommissioned: 3.7 GW

NPP construction roadmap according to the General Plan till 2020

February 2008

Ros

tov,

Uni

t 2

com

plet

ion

Kur

sk,

Uni

t 5*

com

plet

ion

Kal

inin

, Uni

t 4co

mpl

etio

n

NVo

rone

zh-II

, U

nit 1

Bel

oyar

sk,

Uni

t 4

BN

-800

Leni

ngra

d-II,

Uni

t 1

Ros

tov,

U

nit 3

Seve

rsk,

Uni

t 1Tv

er, U

nit 1

Ros

tov,

U

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Niz

hniy

Nov

orod

Uni

t 1So

uth

Ura

ls,

Uni

t 1

NVo

rone

zh-II

, U

nit 2

NVo

rone

zh-II

, U

nit 3 Nvo

rone

zh-II

, U

nit 4

Leni

ngra

d-II,

Uni

t 2

Leni

ngra

d-II,

Uni

t 3

Leni

ngra

d-II,

Uni

t 4

Tver

, Uni

t 2

Tver

, Uni

t 3

Tver

, Uni

t 4

Sout

h U

rals

, U

nit 2

Sout

h U

rals

, u

nit 3

Sout

h U

rals

, U

nit 4

Seve

rsk,

Uni

t 2

Niz

hniy

N

ovor

od,

Uni

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Niz

hniy

N

ovor

od,

Uni

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Niz

hniy

Nov

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, U

nit 4

Cen

tral

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Cen

tral

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nit 3 C

entr

al,

Uni

t 4

NVNPP, Unit 3

NVNPP, Unit 4

24

NPPs in operationNPPs under construction

Prospective NPPs

NPP siting in accordance with the General Plan

Bilibino

Vilyuchinsk (PATES)

Primorye

Kola

Pevek (PATES)

Seversk

South Urals

Leningrad

Kalinin

Balakovo

Beloyarsk

Rostov

Kursk

Tver

Smolensk

Novovoronezh Nizhniy Novgorod

In operation - 31 unitsUnder construction - 10 units (including floating units - PATES)Prospective - 28 units (including floating units - PATES)Upgrading - 14 unitsDecommissioning - 9 units (including Bilibino NPP)

Central

Baltic

Power unit information

2525

The AES-2006 design is the basis for implementation of the General Siting

Plan “roadmap”

2626

● Thermal power has been increased up to 3200 MW and Efficiency factor (gross) of a power unit has reached 36.2%, due to:

▬ elimination of excessive conservatism▬ improvement of steam turbine thermal circuit▬ improvement of steam parameters at the steam

generator outlets and decrease of pressure losses in steam lines

● Economic efficiency has been improved by means of:▬ optimization of passive and active safety systems

used in AES-91 and AES-92 designs▬ unification of the main equipment;▬ decrease of materials consumption

AES-2006 – the targets reached

2727

Negative effects of the world financial crisis

►Industrial production shrinkage

►Energy consumption recession

►Grid restrictions and NPP generation reduction

►Decreased profits and reduced investments in construction of new NPPs

28

2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018 2019 2020

Projects in theconstruction phaseProjects ready forimplementationSpecial projects

As both the economics and electricity demand will be recovered, it is expected to build:Central NPP;Nizhniy Novgorod NPP;Seversk NPP;South Urals NPP;Tver-II NPP

Rost

ov N

PPpo

wer

uni

t 2

Kalin

in N

PPpo

wer

uni

t 4

Nov

ovor

onez

h-II

NPP

Pow

er u

nit

1Le

ning

rad-

II N

PPpo

wer

uni

t 1

Rost

ov N

PPPo

wer

uni

t 3

Leni

ngra

d-II

NPP

pow

er u

nit

2

Rost

ov N

PPPo

wer

uni

t 4

Leni

ngra

d-II

NPP

pow

er u

nit

3

Balt

ic N

PPpo

wer

uni

t 2

Leni

ngra

d-II

NPP

pow

er u

nit

4

Belo

yars

k N

PPPo

wer

uni

t 4

(BN

-800

)N

ovov

oron

ezh-

II N

PPPo

wer

uni

t 2

Balt

ic N

PPPo

wer

uni

t 1

NPP units currently under construction

2929

NPPs under construction – current status

►Completion of NPPs with VVER-1000 reactors:- Rostov NPP, power units 2, 3 and 4- Kalinin NPP, power unit 4

►Construction of NPPs of the AES-2006 design: - Novovoronezh-II NPP, power units 1 and 2- Leningrad-II NPP, power units 1 and 2

►Construction of NPP with BN-800 reactor:- Beloyarsk NPP, power unit 4

►Construction of floating nuclear cogeneration plant (PATES) with KLT-40 reactor (Vilyuchinsk)

3030

Rostov NPP Units 2, 3 and 4

Rostov NPP Unit 2

Rostov NPP Units 3,4

3131

Kalinin NPP Unit 4

3232

Novovoronezh-II NPP

3333

Leningrad-II NPP

3434

Beloyarsk NPP Unit 4

3535

Floating nuclear cogeneration plant (PATES)

36

NPP-2006 siting licenses for new sites

NPP License obtaining date Seversk NPP 13.11.2009

Nizhniy Novgorod NPP 3rd quarter of 2010

Tver NPP 3rd quarter of 2010

Leningrad-II NPP (Units 3 and 4) 2nd quarter of 2010

Baltic NPP 19.02.2010Central NPP 2nd quarter of 2010

37

Main areas of optimization in AES-2006

Economic requirements and boundary conditions of the

Customer

Basis – AES-2006 design

Reactor unit Turbine hallHeat exchangers Safety systems

Auxiliary systems:•Ventilation,•Radwaste

Automated process control system

AES-2010 (VVER-SOC)

Design is not changed.Removal of conservatism

Variability. Optimization. Simplification of the design and completion of passive safety justification

Optimization Development in accordance with the adopted design

Significant upgrading (there is a significant back-up)

38

Development areas for AES-2010 concept design

Area CommentsCost and risks analysis for introduction of new advanced plant equipment and systems :- reduced number of control rods;

R&D works accomplished

- introduction of new main circulation pumps (water lubrication, one-speed motor);

R&D works to be accomplished in 2010

- implementation of new steel for pressure vessels;

R&D works to be accomplished in 2011

39

Development areas for AES-2010 concept design (continuation)

Area Comments- implementation of new set of heat exchanging equipment of collector-platen type;

The collector-platen arrangement of heat exchanging devices will allow to reduce metal consumption

- transition to a deaeratorless layout of the secondary circuit;

The transition will allow to achieve significant savings as regard to Turbine hall equipment & systems

- introduction of heat accumulators to ensure maneuverable parameters of a power unit

Application of heat accumulators will enable the NPP power units involved in maneuvering regimes to maintain the high LF levels and up-to-date fuel cycle parameters

40

Development areas for AES-2010 concept design (continuation)

Area Comments- abandon the demineralizer use, or transition to low-capacity demineralizers;

This is connected with application stainless steels or titanium for heat exchanging surfaces in the secondary circuit and with transition to ethanolamine-based water chemistry

- optimization of the secondary circuit feedwater system arrangement

Introduction of feedwater pump capacity control by means of smooth variation of pump rotation speed. Analysis of application of:- a high-speed rotating turbine drive, a frequency-controlled motor drive;- a motor drive with hydraulic clutch

41

Development areas for AES-2010 concept design (continuation)

Area Comments- implementation of MOX fuel

Analysis of feasibility to implement the EUR requirement concerning MOX fuel use

- introduction of hydrogen-potassium water chemistry for the primary circuit coolant

Will allow to:- minimize equipment composition and dimensions;- optimize service parameters of the water chemistry maintenance systems;- reduce significantly volume of process waste being generated

4242

● Low efficiency in beneficial use of mined natural uranium – less than 1%

● Continuously growing volumes of SNF and RW

Systemic problems of the modern nuclear power

43

1. Economical efficiency 2. Guaranteed safety3. No limitations in regard to a raw materials

base for а historically significant time span4. SNF and RW management – the NP fuel cycle

is to be organized in a way ensuring safe ultimate RW confinement

5. Energy production scale – the share in the national electricity market should be not less than 30%

6. Energy production structure is to ensure an opportunity to expand the markets

Requirements to a nuclear power system (NPS)

44

A power unit of the 4th generation with a sodium-cooled fast reactor:

►Complying with the requirements of large-scale nuclear power in areas of fuel utilization and minor actinides management

►With improved technical, economic performance and safety features

4545

Requirements to VVER technology development aimed at its application in combination with breeder reactors

within the closed NFC:

Fuel utilization (Breeding Ratio)

Efficiency coefficient Investment payback terms

46

Target features of an innovative NPP unit based on the traditional

VVER technology►Fuel utilization – possibility of operation with

breeding ratio (BR) of ~ 0.8 – 0.9 and natural uranium consumption of 130 – 135 t/GW(e) per year

►Thermodynamic efficiency - improvement of the efficiency coefficient by optimization of the steam generator design and by the maximum possible increase of steam parameters

► Investment payback – shortening of the construction period down to 3.5 – 4 years due to the enlarged industrial modular fabrication

47

Today Mid of 21-st centuryBasic electricity supply

Electricity supply, extra fuel breeding

Electricity supply + fuel breeding

Heat supply + electricity

High potential heat, new energy carriers

VVER-440 NPPs,VVER-1000 NPPsRBMK NPPs

BN-600 NPP

Bilibino NHPP

Open nuclear fuel cycle

AES-2006, AES-2006МNPPs with VVER-1000

NPPs with Super-VVER for operation in CNFC with BR ~ 0.9BN-800 NPPscommercial breeders

Regional NHPPs with small- and medium-size reactors

High-temperature reactors

Closed nuclear fuel cycle

Perspective pattern of Russiannuclear power system