AFCEN and ETCC development V1a · ETCCinheritstheexperienceofRCCETCC inherits the experience of...

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Association Française pour les règles de conception de construction www.afcen.com AFCEN General Organization and de conception, de construction et de surveillance en exploitation des matériels des Chaudières Electro-Nucléaires AFCEN General Organization and ETC-C Code roadmap Part A: AFCEN Organisation and objectives Part B: ETC-C main features, examples B1 History of ETC-C B2 ETC-C Characteristics B3 Safety objectives and implications B4 Application examples Part C: ETC-C Development Roadmap Claude DUVAL , AFCEN Editorial Committee ETC-C Subcommittee Chairman IAEA Workshop on Construction Technology for New Nuclear Power Plants December 13 th , 2011. Paris.

Transcript of AFCEN and ETCC development V1a · ETCCinheritstheexperienceofRCCETCC inherits the experience of...

Page 1: AFCEN and ETCC development V1a · ETCCinheritstheexperienceofRCCETCC inherits the experience of RCC-G

Association Française pour les règles de conception de construction

www.afcen.com

AFCEN General Organization andde conception, de construction

et de surveillance en exploitation des matériels des Chaudières Electro-Nucléaires

AFCEN General Organization andETC-C Code roadmap

Part A: AFCEN Organisation and objectives

Part B: ETC-C main features, examplesB1 History of ETC-C B2 ETC-C CharacteristicsB3 Safety objectives and implicationsB4 Application examples

Part C: ETC-C Development Roadmap

Claude DUVAL , AFCEN Editorial CommitteeETC-C Subcommittee Chairman

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris.

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Part A: Presentation of Part A: Presentation of AfcenAfcen--General organizationGeneral organizationThe The AfcenAfcen CodesCodes

PWR tPWR reactors : RCC-M Mechanical components RCC-C Nuclear Fuel RCC-E Electrical Equipment RCC-G/ETC-C Civil Works RSE M In service surveillance of mechanical components RSE-M In-service surveillance of mechanical components ETC-F Fire protection

FBR and experimental reactors : RCC-MR Mechanical components of FBR reactors RCC-MRX (high temperature structures Research Reactors and ITER vacuum RCC-MRX (high temperature structures, Research Reactors and ITER vacuum

vessel -To be published by AFCEN – draft available)

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 2

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Part A: Presentation of Part A: Presentation of AfcenAfcen--General organizationGeneral organizationAfcenAfcen publicationspublications

NEW 2011

AFCEN codes edited in French and English

( bi d P d CD R(combined Paper and CD-Rom versions)

Other translations with Afcen agreements (Chinese)

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman

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Part A: Presentation of AfcenPart A: Presentation of Afcen--General organizationGeneral organizationAfcen structureAfcen structure

EDF + AREVA + CEA + new members in 2010S/comRCC-E

S/comS/comETC-C

RCC-MGENERAL ASSEMBLY

Training committee

S/comRSE-M

Editorial committee

BOARD

S/com

S/comETC-F

& Executive Committee

S/comRCC-C S/com

RCC-MRx

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman

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Part A: Presentation of Part A: Presentation of AfcenAfcen--General organizationGeneral organizationA structure based on codes subcommittees (SC)

BOARD

Edit i l itt G l S t i tEditorial committee

RCC-E Subcommittee

RCC-M Subcommittee

RCC-MRxS b itt

RSE-M S b itt

ETC-F S b itt

ETC-C S b itt

RCC-C S

Training Committee General Secretariat

Subcommittee Subcommittee Subcommittee Subcommittee

WG DesignGeneral GTRx1 Design Analysis

SubcommitteeSubcommittee

Safety and design

Subcommittee

Design

MaterialsGenerality NDEGeotechnicaland soils

Concrete structures

Analysis of products

GTRx2S MaterialsConstruction and installation

TechnologyInstallation Interventions

ExaminationSoftware GTRx2s Fabrication Surveillance

Liner, pool, vessels

Metallic constructions

Manufacture

Inspections

GTRx2S ExaminationInsurance requirements

Qualification

Examination

Anchors andfixings

GTRx2s Welding

Test andMonitoring

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman

Examination

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Part A: Presentation of Part A: Presentation of AfcenAfcen-- Development policy:Widening and opening Widening and opening AfcenAfcen

New statutes since 2010

New members joined AFCEN

New contributors expected in the Sub Committees

International cooperation, based on specific organization with shared experts

Enhancing adaptation of codes to International context

Develop a strong cooperation and feed back between AFCEN and foreign members

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 6

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Part B : ETC-C main features

B Today status and evolution

B1 History of ETC-CB1 History of ETC-C

B2 ETC-C Characteristics

B3 Safety objectives andimplications

B4 Application examples

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 7

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B1 History of ETCC

“ETC” codes = EPR Technical Codes Specific Nuclear Design Codes initially developed by EDF and

German Utilities (previously RCC codes in France) Assessed by French Safety - ASN / and currently by UK HSE

ETCC Obj ti ETCC Objectives : ETCC describes the principles and requirements for safety,

serviceability and durability conditions of concrete andserviceability and durability conditions of concrete and steelworks structures, together with specific provisions for safety-class buildings of EPR

ETCC is a design code specific to EPR ETCC is a design code specific to EPR Historical basis of ETCC :

ETCC inherits the experience of RCC-G ETCC inherits the experience of RCC-G ETCC collects the design experience feedback of a number of

prestressed containments and structures which were erected

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 8

using the same or very similar safety concept

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B1 History of ETCC

RCC-G Series RCC-G 1980: EDF Document

• Applicable to 900 Mwe series• Enforced by RFS V.2.b

RCC-G 1985 rev 2 (juillet 1988) – AFCEN Document• Enforced by RFS V.2.h (13/10/1988)• Applicable to 1300 Mwe series for modifications and verifications • Applicable to N4 seriespp

ETC-C ETCC 2006 – EDF Document

• Used for FLAMANVILLE3 Preliminary Safety Analysis Report• Used for FLAMANVILLE3 Preliminary Safety Analysis Report, AFCEN ETCC 2010 : AFCEN Document issued end of 2010.

• Based on ETCC 2006• Reflects the experience gained from Flamanville3 development• Reflects the experience gained from Flamanville3 development• Incorporates evolutions driven by the discussion with Safety Authorities (UK…)• Used fo UK EPR Generic Design Assessment.

To be used for next EPR projects

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 9

• To be used for next EPR projects

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B2 ETCC Characteristics

ETCC Characteristics Safety :

• Safety requirements are considered in the design of each building• Safety requirements are considered in the design of each building of the NI: actions and combination of actions

Eurocodes : • ETCC is based on the limit state concept as developed in

Eurocodes EN1990, EN1991, EN1992 and EN1993 and adapted to this particular project

Design situations (fundamental, accidental) are distinguished in compliance with the safety concept of Eurocodes

• Partial load and design resistance factors for normal (conventional)Partial load and design resistance factors for normal (conventional) combinations of actions are adopted according to EC2

• Accidental situations and related requirements associated with EPR

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 10

EPR

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B2 ETCC chapters

PART 0 ; General0.1 Structure of ETCC

PART 2 : Construction·2.0 General principles2 1 E h k d il0.2 General provisions

PART 1 : Design1.1 Scope

·2.1 Earthworks and soil treatment·2.2 Concretes·2.3 Surface finishing and formworks·2.4 Reinforcement of reinforced concrete

·1.2 Principles et references·1.3 Definitions of actions and load combinations·1.4 Gen rules for concrete structures·1.5 Metal parts involved in the leak tightness of

the containment

·2.5 Prestressing system·2.6 Prefabrication for concrete element and

reinforcement cages·2.7 Leaktight metal part of containments

the containment·1.6 Pools and tanks with liners·1.7 Structural steelwork·1.8 Interface requirements between anchors and

concrete

·2.8 Metal elements incorporated into the concrete·2.9 Metal liner of watertight pool and tanks·2.10 Structural steelwork ·2.11 Buried safety classified pipelines

1.9 General rules for geotechnical design·Appendices

-1A Seismic analysis -1B Creep and shrinkage strains and cracks of concrete-1C Engineering method for military aircraft impact verification and

d d l d

·2.12 Filling of joints ·2.13 Topography, tolerances, and monitoring·Appendices

dropped loads-1D Penetrations of reinforced and prestressed concrete slabs by hard

issiles. –-1E Glossary for the analysis of metal parts involved in the leaktightness

of the containment.-1F Calculation of the static force equivalent to certain accidental actions.- 1G (Informative) : Tables of requirements

PART 3 monitoring (containment leaktightness)3.1 Terminology3.2 General provisions 3.3 Leaktightness tests

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 11

1G (Informative) : Tables of requirements- 1H Shear resistance of reinforced concrete structures

3.3 Leaktightness tests3.4 Resistance tests and containment monitoring

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B2 Safety objectives

Plant conditions PCC1 : Normal operating

Internal hazards High energy piping failurep g

transients PCC2 : Design basis transients PCC3 : Design basis incidents

High energy piping failure Internal flooding Internal missile Load drop PCC4 : Design basis accidents

Risk reduction category (multiple failures)

Load drop Fire

External hazards RRC-A : prevention of core melt RRC-B : prevention of large

releases in core melt (severe accident)

Earthquake : • OBE operating basis earthquake, • Design Basis Earthquake

accident)

Margins To cover uncertainties

Airplane crash External explosion Groundwater level

To cover uncertainties For external hazards LOCA 2A, SLB LOCA +EQ

External flooding Weather events

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 12

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B2 From safety objectives to CW design conditions

Design conditions Normal conditions : (normal operating) serviceability,

• Pressure and Temperature inside containement• Pressure and Temperature inside containement• Equipment and piping induced Loads • External : air T°, snow, wind, water table

Exceptional : (>= 1 time during lifetime) resistance leaktightness Exceptional : (>= 1 time during lifetime) resistance, leaktightness• P & T for PCC2 events• Piping Service Tests loads, containment pressure testing

E t l f i d t l T° t t bl t i l l• Extreme values for snow, wind , external T°, water table centennial value• OBE , operating basis earthquake

Accidental : (in depth defence) irreversible deformation admitted• P&T for PCC3 and PCC4 events, RRC-A conditions• DBE Design Basis EQ • Airplane crash protection,• External explosion pressure wave• High Energy piping rupture, Internal missile

Construction phase

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 13

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B2 Functional capabilities of structures

Functional capability of Structures ABB: serviceability of concrete structures – behaviour not modified RBB: capacity of the concrete structure to withstand the applied loading (permanent

deformation of structures allowable to the extent that they remain stable) and integrity of connected equipment maintained

AMM: serviceability of steel structures, including their integrity – avoidance of tearing required for cladding, but without associated leak criterion,

RMM: structural capacity of penetrations in accident situations – permanent MM p y p pdeformation allowable to the extent that the penetrations remain functional

C: capacity to contain radioactive materials. It applies mainly to the inner containment, with an associated leak criterioncontainment, with an associated leak criterion

E: leak tightness of fluid containers - integrity ensured even with permanent deformation

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 14

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B2 Identification of safety important buildings

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B2 Severe accident design implications

External thick containment shell

Containment designed for P & T - severe

accident scenrio

(airplane crash)

AccesDiv2 Div3

Div1 Div4RB

Core melt spreading areaFuel

NAB

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 16

Core melt spreading area Accès matérie

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B3 Application to Reactor Building

An example : functional capability requirements for the reactor building

ConditionsOuter containment

(concrete shell)Inner

containment

Raft Liner and penetrations ETCC: Groups of load combinations

nt

Normal, exceptional (PCC-2 , Inspection

Earthquake andABB (Serviceability) C (Containment)

+ AMM (integrity)Earthquake and environment)

Periodic testsABB (Serviceability)

Group 1C (containment)+ AMM (integrity)

AMM (integrity)

ABB + C ABB

Design Earthquake(PCC-3 & PCC-4) C (Containment)RBB (Resistance)

ABB (Serviceability) AMM (integrity)Leakrate = 0,155 v/j

Group 2

BB BB

Severe Accidents,combination of

Leakrate = 0,3 v/jRBB (Resistance)

RBB (Resistance) Group 3C (Containment)

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman

LOCA and earthquake

BB ( ) ( )

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B4 Application to Reactor Building Concrete structure

D i f h i l f i i For Group 1 (normal operation, tests) :

- In current zone, pre-stressing is such that the mean stress remains compressive under test conditions

 

Design of the containment : examples of criteria

remains compressive under test conditions- In tensile zones, on the inner surface of the wall, membrane tension is taken up by the passive rebars while overstress in the pre-stressing cables is limited to 0.1 fpk (fpk characteristic strength of the cables)strength of the cables)- Tensile stress for steel reinforcement exposed to bending moment limited to 290 MPa (fyk = 500 MPa)

F G 2 (LOCA S A D i E th k ) For Group 2 (LOCA , S A, Design Earthquake)- Mean stress in the wall remains compressive under accident conditions (liner thermal thrust) to control the appearance of cracks in the singular zones - Tensile stress in flexural rebars and shear reinforcement limited to 0.8 fyk

For Group 3 (Increased SA, LOCA+DE)For Group 3 (Increased SA, LOCA DE) - The ultimate deformation of the material is used as a criterion-Tensile stress in flexural rebars and shear reinforcement limited to f

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman

limited to fyk

Fig.1 EPR reactor building

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B4 ETC-C : Concrete structure

B4 Shrinkage assessmentShrinkage has to be carefully taken into account especially in the thickest zones likeShrinkage has to be carefully taken into account especially in the thickest zones like the foundation raft and the junction between cylinder and basemat. ETC-C is compliant with EN 1992-2 (dedicated to bridges).

600

700

ε r (μm/m)

Humidity Level= 50%

400

500

raft

50%

100

200

300raft

500 mm Wall

0

100

0 5000 10000 15000 20000 25000

Time (days)

65 years

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman

65 years

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B4 Concrete structure

Shear strength

The minimum value of the angle θ isdetermined in relation to the axial force

For high compressive stress (σcp ≥ 0), θ canqσcp For high compressive stress (σcp ≥ 0), θ can

be small (struts are very tilted) then :

Where cp 2021cot

θ

σcp is the concrete stress perpendicular to the section is the mean value of concrete tensile strength

ctmf

2.02.1cot

fStrut Shear reinforcement

qFlexural rebars

For tension (σcp < 0) struts cannot be tilted then:

ctmfσcpq

θ

  19.02.1cot ctm

cp

f

θ

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman

ctmf

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B4 steel liner of the containmentDesign principles

The metallic liner is considered as being linked to the concrete in a continuing mannerto the concrete, in a continuing manner without sliding.

The thermal expansion of the liner is restricted leading potentially to the blistering

Dome

External walkway(construction)

Dome

External walkway(construction) restricted, leading potentially to the blistering.

Initial shape imperfections leads to consider the blistering as a normal mode of deformation

Polar cranebrackets

Upper part

Polar cranebrackets

Upper part deformation.

On the common zones, the membrane strains are constant along the sides of a mesh (delimited by continuous anchorages)

Upper partUpper part

(delimited by continuous anchorages) .

Inside a mesh three cases are to be considered :1. A mesh with or without defect submitted to traction

Lower partLower part

2. A mesh with defect submitted to compression : increasing blistering

3. A mesh without defect submitted to compression : buckling analysis (critical load determination)

Raft part Raft part

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman

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B4 Containment penetrations

Different types of penetrations Design rules for penetration sleeves

Penetrations are designed to accommodate all loads and deformations without loss of

Bellows

Outer wall Inner wall

Equipment hatch

Seals

Metal liner

structural and leak-tightness integrity They are designed to resist both mechanical

loads (pipe reactions, containment pressure) and displacement limited loads (thermal

Site access

Bellows and displacement limited loads (thermal expansion, concrete pre-stressing)

For normal operation situations (level 1), a classical elastic analysis is required.

Bellows

Standard piping penetration

Personnel air-lock

For accidental situations (levels 2 and 3), a limit analysis with a material perfectly plastic is required.F ll it ti b kli l i i

Bellows

Bellows

Transfer Tube penetration

e so e a oc

For all situations a buckling analysis is required

Electrical penetrations

Bellows

Penetration for steam and water pipes

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman

Limit of supply

Page 23: AFCEN and ETCC development V1a · ETCCinheritstheexperienceofRCCETCC inherits the experience of RCC-G

B4 ETC-C : Pools and Tanks liner

Design requirements Design requirements The liners of internal surfaces of pools or concrete tanks are :

• designed to ensure water-tightness and to collect any potential leaks at the weldweld

• Playing no structural part in term of resistance but transmitting the hydrostatic loads to the concrete

• Submitted to thermal loads ETC-C rules

According to these requirements ETC-C gives prescriptions about • Material (thin austenitic stainless steel)• Limitation of the unavoidable buckling of the thin plates• Design of the anchoring systemDesign of the anchoring system • Specification of the minimum distance between anchors taking into

account the cracking of the concrete

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman

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C1 ETCC Development Roadmap

Key objectives for further development Incorporate relevant modifications : Incorporate relevant modifications :

• Results of discussion with safety authorities • New construction techniques and associated criteria

Associate industrial companies (owners, design, construction…)• Incorporate their experience

I t ffi i t i d t i l ti• Incorporate efficient industrial practices

Open to international membership• UK, China...

Develop training programs : • 1 Session in October 2011 : Design• 1 Session in 2012 fall : Construction• 1 Session in 2012 dedicated to International members (in English)

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 24

( g )

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C1 ETCC Development Roadmap

Short term objectives and calendar : Improving AFCEN ETCC 2010 Improving AFCEN ETCC 2010

• ETCC 2010 was issued at the end of 2010• To correct editorial mismatches• To implement relevant modification resulting from Safety Bodies

assessment

Developing a new Code for New Design (RCC-CW 2013)• Incorporate adequate design rules for new design features

Adapting the Codes to new contexts• Country specific or Project specific Companion Documents /y p j p p

Appendices• Training sessions in English• Opening the Subcommittee to new AFCEN members (UK China )

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman

• Opening the Subcommittee to new AFCEN members (UK, China...)

25

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C2 ETCC Subcommittee

ETCC Subcommittee 1 Chairman, 6 TG leaders AFCEN founding Members 1 Chairman, 6 TG leaders 20 SC members 80 Experts in task groups

EDF CEA AREVA

Design and Construction companies

ETCC SC

ETCC Subcommittee

p EGIS BOUYGUES VINCI

TG1 Safety, Design & Structure of code

TG2 Geotechnics, soils and buried t t VSL

International NNB (UK)

structures TG3 Reinforced and pre-stressed

Concrete structures TG4 Containment & pool liners ( )

CNPRI (China) ……..

Link with Safety

TG4 Containment & pool liners, storage tanks

TG5 Metal frame structures TG6 Anchorages

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 26

y IRSN as observer

TG6 Anchorages TG7 Tests and monitoring

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C3 AFCEN ETCC: an industry answer

ParliamentLaws

Government

Laws

Decrees(executive)

ec ees

OrdersBinding

Decisions

Guides

Non binding

Technical Codes and StandardsUtility / Industry / Organizations(approved or assessed by ASN)

Utility (assessed by ASN or at ASN’s disposal)

Project documents

( pp y )

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 27

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www.afcen.com

To be completed

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 28

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Thanks for your Attention THANKS YOU FOR

y

ATTENTION

IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 29