Needs in R&D Supporting Nuclear Power Plant Life Management · Needs in R&D Supporting Nuclear Power Plant Life Management Michel Bièth, P. Contri, N. Taylor Nuclear Operation and

Shanghai, 17 October 2007 – Michel Bièth 1

Needs in R&D Supporting Nuclear Power Plant Life Management

Michel Bièth, P. Contri, N. TaylorNuclear Operation and Design Safety

European CommissionJoint Research Center - Institute for Energy

IAEA Second International Symposium on Nuclear Power Plant Life Management, Shanghai, China, 15-18 October 2007

[email protected] http:// ie.jrc.cec.eu.int email:[email protected]


European Commission(25 Commission members)

Panorama of the European UnionEuropean Court

of Auditors European Parliament

The Councilof the

European Union

The Committee of the Regions

Court of JusticeEconomic and

Social Committee

RELEX ENTR ENV SANCO JRC…

IES

... ... ...

IEIPSC IPTS

...... RTD

IRMM ITUIHCP

SG


… to provide customer-driven scientific and technical support for the conception, development, implementation and monitoring of EU policies …

…the JRC functions as a centre of science and technology reference for the EU, independent of special interests, private and national

EC-JRC Mission

Shanghai, 17 October 2007 – Michel Bièth 4Structure of the JRC

7 Institutes in 5 Member States ≅ 2900 staffIE - Petten The Netherlands-Institute for Energy

IRMM - Geel Belgium- Institute for Reference Materials and Measurements

ITU - Karlsruhe Germany - Institute for Transuranium Elements

IPSC - IHCP - IES - Ispra Italy- Institute for the Protection and Security of the Citizen- Institute for Health and Consumer Protection- Institute for Environment and Sustainability

IPTS - Seville Spain- Institute for Prospective Technological Studies


EC Nuclear illustrative Programme (NIP)

Art. 40 Euratom treaty mandates the European Commission to prepare NIP– Periodically published, since 1958 four NIPs prepared– Both quantitative and qualitative description of the current andfuture status of nuclear industry

– 2006 NIP: Independent of the energy policy choices made by EU Member States (MS), consistent action in the field of nuclear safety and waste management is necessary


(Nuclear ~ 32% of total EU electricity production)

NL, 0.4%

RO, 0.5%

SI, 0.6%

LT, 1.1%

HU, 1.4%

SK, 1.7%

BU, 1.8%Other 12.4%

FI, 2.4%

CZ, 2.5%BE,4.8%

SP, 5.8%

SE, 7.3%UK, 7.9%

GE, 16.3%

FR, 45.5%

Source PRIS

MS Share of nuclear generation in EU27EU Electricity sourcesNuclear: 32%Coal: 30%Gas: 20%Hydro: 9.5%Oil: 4.5%


EC Nuclear illustrative programme (NIP)• Key issues addressed

– Current status of nuclear sector in EU 27

– Common nuclear safety reference levels in EU

– High Level Group on Nuclear Safety and Security

– National plans for Decommissioning and Radioactive Waste Management

– Near-term investment plans for new resources

– Technology platforms for closer coordination of research (both European Community as well as national industrial programmes)


EC Nuclear Illustrative Programme (NIP)

NIP conclusions– Nuclear power significantly contributes to EU’s energy mix– Nuclear energy is essentially CO2 emission free– Global demand for nuclear power is expanding

However– It is on MS to decide whether to use nuclear energy– Community should adopt a legal framework– Ageing of existing NPPs has to be effectively managed– Life extensions and/or construction of new NPPs may be required


European Council Decision (9 March 2007)

“…it is for each and every Member State to decide whether or not to rely on nuclear energy and stresses that this has to be done while further improving nuclear safety and the management of radioactive waste, and to that effect it:Supports R&D on waste management, particularly under the FP7– Can envisage the creation of a high level group on nuclear safety and waste management […harmonisation of approaches, analysis of operating experience, addressing safety issues…] …”


EU Nuclear Research programme• Legal basis

– Established by Euratom treaty (1957)– Legally separated from European Economic Community treaty– Has its own Framework Programme (currently 7th FP)

• Objectives– Support competition – Support development and implementation of EU polices– Implemented by EC RTD (indirect actions) and JRC (direct actions)


Nuclear research and training activities (indirect actions) (2234 M€)– Fusion energy (1947 M€)– Nuclear fission and radiation protection (287 M€)

• Management of radioactive waste• Reactor systems• Radiation protection• Support for and access to research infrastructures• Human resources and training including mobility

JRC (direct actions)

EuratomEuratom FP7 FP7 (2007 – 2011)

Shanghai, 17 October 2007 – Michel Bièth 12JRC FP7 Nuclear ProgrammeJRC FP7 Nuclear Programme

Nuclear Safety and Security

Nuclear Security

Nuclear Safety

Waste Management, Environmental Impact & Basic Knowledge

46 % (+)

24 % (-)

30 % (0)

High Flux ReactorDecommissioning&Waste Management


EURATOM Framework Programme 7 (2007-2011)

The Framework Program 7 (FP7) (Council decision 18/6/2006) in the area dedicated to the reactor systems calls for a research effort “to underpin the continued safe operation of all relevant types of existing reactor systems (including fuel cyclefacilities), taking into account new challenges such as life-time extension and development of new advanced safety assessment methodologies (both the technical and human element)”.

The safety of nuclear installations theme includes:– plant life assessment and management, safety culture, advanced safety assessment methodologies, numerical simulation tools, instrumentation and control, and prevention and mitigation of severe accidents, with associated activities to optimise knowledge management and maintain competence.


“in the areas of nuclear energy production, its safety and reliability, its sustainability and control, its threats and challenges and its future exploitation potential, including safety and security of innovative/future reactor systems”. In particular, three “agendas” implement these objectives, namely:

– Agenda n.1: Nuclear waste management and environmental impact

– Agenda n.2: Nuclear safety, aimed at maintaining and improving the safety level of both Western and Russian type of nuclear power plants, and at extending and validating advanced and refined safety assessment methodologies and corresponding analytical tools

– Agenda n.3: Nuclear security

Multi annual work program of EC-JRC


Nuclear Safety Priorities at the JRC-IEWith reference to the agenda n.2, the JRC further developed the workplan identifying the following research areas for activities to be carried out at the Research Centers:– Long term safe operation of both Western and Russian power reactor types. This is particularly important for continued power production in areas where no immediate alternatives exist. In the hypothetical case of an accident happening, efficient and effective mitigation of its effects is also crucial.– Plant risk and safety assessment. State-of-the-art tools, experimental facilities and procedures are needed in this area to support the validation of the relevant safety assessment models. This is of prime relevance to plant long term operation.


ACCIDENT PREVENTION:Integrity of the Reactor Coolant System

ACCIDENT PREVENTION:Integrity of the Reactor Coolant System ACCIDENT MITIGATION:

Integrity of the Confinement SystemACCIDENT MITIGATION:

Integrity of the Confinement System

with investigation on:�material’s degradation(irradiation, corrosion, thermal fatigue)� in-service inspection� structural integrity� preventive maintenance

with investigation on:�material’s degradation(irradiation, corrosion, thermal fatigue)� in-service inspection� structural integrity� preventive maintenance

with investigation on:� accident analysis(test interpretation, code validation) - ‘severe accidents’� accident management� system interaction

with investigation on:� accident analysis(test interpretation, code validation) - ‘severe accidents’� accident management� system interaction

Horizontal activities:� probabilistic & risk assessment methodologies� data management & dissemination� training

Horizontal activities:� probabilistic & risk assessment methodologies� data management & dissemination� training

Nuclear Safety at JRC-IE


SAFEWASTE Waste packages and facilities for transport, storage and disposal of high-level nuclear waste and spent fuel

NCT Development and Exploitation of Neutron Capture TherapyAMA Analysis and Management of nuclear Accidents

SAFELIFE Safety of Ageing Components in Nuclear Power PlantsSONIS Safe Operation of Nuclear InstallationsNUSAC Nuclear Safety Clearinghouse for

Operational Experience Feedback

SAFETY-INNO Safety of innovative reactors design

FP7 Nuclear Safety projects at EC-JRC

- ISI and Maintenance- Fire safety, seismic- Organisational issues

- Component integrity- Ageing management- Specimen Surveillance


Contribution to PLIM• Operating organisation• Interfaces with the Regulatory Body• Quality Assurance• Feedback of operating experience• Physical protection• Fire safety• Emergency preparedness• Qualification and training of personnel• Plant operation• Maintenance, testing, surveillance and inspection of SSCs• Radiation Protection• Plant modifications• Periodic Safety Review (and plant life extension)• Decommissioning

SONIS and NUSAC

According to the IAEA Safety Requirements for Operation – NS-R-2

Content of operation safety


Design related issues for PLIM

• Component integrity– Stress corrosion cracking– Radiation Damage– Thermal fatigue– Residual stresses– Assessment of defects through qualified ISI

• Knowledge management for design skills


Conduct of the JRC research for PLIM through Networks• Integrate fragmented R&D on maintenance, structural integrity and ageing through actions at European level

• Involve end-users to prioritise the activities

• Promote best practices and enhance nuclear safety expertise


NUclear Plant LIFE Prediction NULIFE Network of Excellence

To create a single organisational structure capable of working at European level to provide harmonised R&D in the area of lifetime evaluation methods for structural components to the nuclear power industry and the relevant safety authorities.

Co-financed by EC-RTD; Coordinator: VTT

JRC picture

NULIFE


NULIFE Contractual Structure

Collaborators10 Contractors

AssociateContributors

(27)

SercoForsmark

NRISCK·CENVTT

BEJRC

Areva GmbHEDFCEA

EU/EC


SONIS (Safety Operation of Nuclear Installations): SENUF+ENIQ+other research topics

SONIS

To face the technical, research and organisational issues in Operational Safety (for both short and long term operation), with emphasis to optimisedmaintenance programs (SENUF network) and qualifiedISI programs (ENIQ network), effective engineeringprograms (seismic and fire protection) and improved control of human factors


1)Maintenance related issues:• operational performance indicators• reliability centered methods• operational plant life management

2) Effectiveness and efficiency of ISI programmes and strategies

• Risk-Informed ISI• NDT Reliability• Inspection qualification

SENUF SENUF Network Network

FP6FP6

ENIQ ENIQ Network Network

FP6FP6

Follow-up from:

SONIS: Maintenance and Inspection


European Network for Inspection and Qualification

European Utilities Chair/vice: DE/SK

40+ active members: UK, FIN, SE, DE, BE, FR, ES, CZ, SK, HU, CH (IAEA, EPRI)

Utilities, R&D, Vendors

Reg u

latory

Requ

ir eme

nts

R ecommendedPracticesas a basis forharmonisation

ENIQ Steering Committee

Task Group on Inspection Qualification

Task Group on Risk-Informed ISI

(probabilistic approach to integrity)

ENIQ network

Towards a harmonisation of Codes & Standards at a European Level


SAFELIFE Key facilities

Stress corrosion cracking in PWSCC/SC-SCC environments

Fracture & Fatigue Testing Microstructural analysis

HFR: LYRA irradiations and neutron beams

Advanced FE simulations

Non-destructive measurements for detection of defects


�RPV modelling: P-Cu and Ni-Mn-Si inclusion� T and fluence rate effects� Cr correction� Adaptation for general use: higher fluence, GEN IV mat., etc.

0

50

100

150

200

250

0 50 100 150 200 250

higher Cr welds

meas

ured

DBT

T shif

t, K

predicted DBTT shift, K

Evidence for Cr stabilisation

0

50

100

150

200

250

0 50 100 150 200 250predicted DBTT shift, K

meas

ured

DBT

T shif

t, K

Cr correction

Evidence for Cr stabilisation of irradiation damage in RPV weld metals, I.J.P.V.P., Vol. 83, Issue 8, Aug.2006, L. Debarberis and H. Hein

Radiation Damage Understanding/Modelling


NESC benchmark tests• The NESC-I test realised a

planned cleavage run-and-arrest event at the large through-clad defect (74 mm). This results confirmed the safety margins of several national nuclear safety codes

• Follow-up projects focusing on shallow-cracks: NESC-II (MPA PTS tests, NESC-IV (ORNL cruciform tests) and VOCALIST

The cleavage event location

Thermal fatigue under turbulent mixing conditions (CFD simulation)

Outer span : 7 m.

Inner span : 3mMaximal load per ram : 2000 kNMaximal ram displacement : 1 m

Outer span : 7 m.

Inner span : 3mMaximal load per ram : 2000 kNMaximal ram displacement : 1 m

ADIMEW test on a safe-end DMW, analysed in NESC-III


Harmonizing methods for assessing postulated RPV flaws

• The behaviour of small sub-surface flaws in the RPV under accident conditions is a critical issue• Advanced techniques offer

potential for ensuring adequate safety margins for long term operation.NESC-I Test (1993-2001):

• Provided experimental confirmation of margins

• benchmark for advanced fracture mechanics and the Master Curve fracture toughness approaches

DG-RTD Vocalist Project (2001-2004): constraint-based fracture mechanicsNESC-IV Shallow Flaw Project: (2000-2006) treatment of surface breaking and embedded flaws

DG-RTD Frame Project (2002-2004): Master Curve validity for irradiated material

IAEA CRPs 8 & 9 consensus guidelines for advanced PTS assessment, including use of Master curve

DG-RTD Smile Project (2002-2005): warm pre-stress effects


• JRC has significant expertise for assessment of damage due to thermal fatigue in NPP piping systems.

• The NESC-TF project (report in May 2007) developed the first phase of the European Procedure

• The second phase is to be developed in NULIFE

European Procedure on Thermal Fatigue under Turbulent Mixing Conditions

The JRC thermal fatigue simulation system; growth of multiple cracks is tracked using ultrasound measurements.

48 mm

14 mm20 mm

224mm

axial load

48 mm

14 mm20 mm

224mm

axial load

Turbulent mixing phenomena is associated with mixing Tee junctions (CFD from NRG)

0.247 0.248 0.249 0.25 0.251 0.252 0.253 0.254-200

-150

-100

-50

0

50

100

150

200

Radial distance (m)

Axial

stres

s (MP

a)

The axial stress profiles, f=1 Hz, epsZ=0

0.25 sec0.75 secFEAFEA

New JRC analytic solutions for through wall stress distributions to use in simplified assessment methods.


Residual stress analysisLarge Component Neutron Diffraction Facility: first stress diffractometer in the world capable of handling 1000 kg components, such as full-scale safe-end weld mock-ups

NET network:analyses of data from the round robins to compare experimental data and numerical simulations for a single bead-on-plate weld specimen completed


Measured TWE versus Reference TWE for all teams weld A

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0 5 10 15 20 25 30Reference TWE in mm

Mea

sure

d TW

E in

mm

� NESC-III project organised by JRC around a RTD-sponsored benchmark test (ADIMEW)� ISI: 7 European teams inspected two pipe welds – stainless steel and Inconel; results show Sizing of defects remains a challenge � Finite element simulations for the ADIMEW crack, illustrating the variability in material properties and crack driving force estimates

–Big scatter in sizing results–Only one team within sizing

target–One defect (19 mm) sized

between 9.5 and 27 mm.

CS304L

308L

SCC Simulation, Defect A9

Buttering

Reference TWE (mm)

Modelling the uncertainties in ISI


European Clearinghouse on Operational Experience Feedback

Operational Experience Feedback is essential for PLIM: Further to the OECD/NEA-IAEA-GRS conference in Cologne (29-31 May 2006) “Improving Nuclear Safety through Operating Experience Feedback”, J. Laaksonen (STUK Director General) made proposals to WENRA (27 June 2006, 5 November 2006, 29 March 2007) to establish EU Clearinghouse at EC-JRC-IE, Petten premisesTo establish at European level an effective system for NPP operational experience feedback and best-practice for assessment of NPP operational events through the use of state-of-the art methods, computer aided assessment tools and information gathered from different EU national regulators and Technical Support Organizations and international sourcesEstablishment in EC-JRC Petten (NL) of a permanent group made of EC-JRC scientific staff and a limited number of Detached Experts from some European Safety Authorities


European OEF System Objectives (as proposed during WENRA March 2007 meeting)

• Screening and evaluation of significant operating experience at European level

• In-depth analysis, taking also into account the differences between NPP designs

• Collection and evaluation of actions taken in different countries

• Generic and/or specific recommendations on actions for ensuring safety

• Further services to safety authorities from EU Member States, as requested



European OEF System Organisation (as proposed during WENRA March 2007 meeting)

• European Information Service Centre (under EC*) to coordinate the OEF System work and to operate a European data warehouse on operating experiences

• European Expert Network composed by TSO & RB experts to carry out the technical analysis within their respective home organizations to benefit from their corresponding resources and working tools resulting in “technical opinions”

• Technical Board composed of representatives of the participating TSO & RB and the Service Centre head in order to define the workprogramme, to review the allocation of resources, to approve therecommendations on safety ensuring actions and to interact with the safety authorities as well as international organisations* EC has proposed to locate it in EC-JRC-Institute for Energy, Pettten (NL)



AdministrationCoordination

CommunicationData Management

ScreeningStorage

Dissemination

International OE

Identified new safety concernsGood practices found relevant

for preventing eventsNational investigation reports

Licensee event reports

Additional Sources

Information Service CenterNational response toRecommendations

Regular Information (Web Site)Feedback on actions taken

Safety authorities

In-depth analysisGeneric evaluationsRecommendationsServices at request

European Expert Network

Technical BoardProgram, Supervision, Approval

Incident Reporting System(IRS)

Quick reporting systems(INES/NEWS)

European OEF System Organisation Scheme(as proposed during WENRA March 2007 meeting)


Support to TACIS nuclear safety• Contribution of EC-JRC to the safety improvement of operating NPPsof Russian design in Russia, Ukraine and Armenia:Assistance of EC-External Relations and EuropeAid Cooperation Office (EC-AIDCO) in charge of the TACIS / INSC programme in all phases from project preparation, to tender evaluation, technical follow-up and review of results

• JRC is technically supporting EC-AIDCO in all areas of TACIS nuclear safety, in particular related to PLIM:– On-Site Assistance and operational safety– Design Safety– Regulatory Authorities and their Technical Support Organisation– Dissemination of TACIS and PHARE projects results: http://www.jrc.nl/dissem/


TACIS, INSC, PHARE and IPA nuclear safety

• TACIS and PHARE nuclear safety funding (1991-2006): – 1100 M€ for TACIS– 250 M€ for PHARE

• New Financial Instruments (2007-2013): INSC (Instrument for Nuclear Safety Cooperation) with worldwide application except EU and candidates countries; and IPA: Instrument for Pre-Accession replacing PHARE and other former instruments

• INSC objectives: - promotion of safety culture at all levels through support of Regulatory Bodies, Technical Support Organizations, and on-site assistance programmes- Improvement of safety aspects of design, operation and maintenance of nuclear power plants (contributing to PLIM of NPPs) and other nuclear installations


Recent or on-going TACIS projects supporting PLIMVVER RPV Embrittlement and Integrity for Reactor Pressure Vessels of VVER 1000 and 440/213 NPPs in Russia and UkraineInvestigation of neutron radiation effects on material properties of titanium steel and welds of VVER internalsImplementation of safety related equipment qualification in UkraineMaintenance equipment for VVER primary loop Establishment of the Ukrainian NDT Training Center for NPP ISI

TACIS Design Safety projects


Contribution to PLIM through large scale modernization projects (PIP) for:• Armenia NPP: Leak Before Break application to Metsamor NPP unit 2

• South Ukraine NPP: Boron Concentration Control and Monitoring System

• Zaporozhye NPP: SG Safety Valves for 6 Unit of ZNPP; Radwaste Treatment Complex

• Rovno NPP: Primary circuit Overpressure Protection System, Radwaste Treatment Facility

• Khmelnitsy NPP: Replacement of Digital Reactor Protection System

• Kola NPP: Liquid Radwaste Treatment Facility

• Balakovo NPP: Computerized Information System for Units 1 & 2

• Kalinin NPP: Replacement of Digital Reactor Protection System and Computerized Information System for Unit 1 & 2

• Smolensk NPP: Radwaste Treatment Facility

• Novovoronezh NPP: New Emergency Feedwater System

• Beloyarsk NPP: Replacement of Safety Valves

Implemented TACIS On-Site Assistance projects since 2004


Nuclear Energy Technology Platform

Launch Conference of the Technology Platform on Sustainable Nuclear Energy (SNE-TP), Brussels, September 21st, 2007Technology Platforms works in 3 stages:– Sharing a agreed common vision among stakeholders

– Reducing the fragmentation of R & D

– Mobilising public and private funding sources


Conclusions

• R&D has a critical role to play in supporting all aspects of PLIM programs

• At European level the European Commission-Joint Research Centre works using networks to coordinate activities in selected areas identified by the stakeholders.

• This approach optimises use of resources and has shown to be effective in promoting best practices for plant life management

Documents

Needs in R&D Supporting Nuclear Power Plant Life Management · Needs in R&D Supporting Nuclear Power Plant Life Management Michel Bièth, P. Contri, N. Taylor Nuclear Operation and