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 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.
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
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
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
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
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
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
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
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
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
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
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
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
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
B2 Identification of safety important buildings
IAEA Workshop on Construction Technology forNew Nuclear Power Plants December 13th, 2011. Paris. C. DUVAL, ETCC SC Chairman 15
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
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 ( ) ( )
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
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
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
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
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
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
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 )
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
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
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
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
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