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Major Innovations in PWR Load Follow Operations by AREVA Anne-Marie Choho Senior Executive Vice President, Engineering & Projects, AREVA Paris, 21st October 2013

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  • Major Innovations in PWRLoad Follow Operationsby AREVA

    Anne-Marie ChohoSenior Executive Vice President,

    Engineering & Projects, AREVA

    Paris, 21st October 2013

  • 2A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Requirements from the Grid

    Impact of Load Follow on French PWR Design

    Industrial Deployment of the Load Follow on French PWR

    Conclusions

    Outlines

  • 3A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Outlines

    Requirements from the Grid

    Impact of Load Follow on French PWR Design

    Industrial Deployment of the Load Follow on French PWR

    Conclusions

  • 4A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    An Exciting Story that began at the end of the 70s…

    From the 900 MW to the EPR TM Units

    Tricastin, Rhone Valley, France EPR Flamanville 3 consruction site, Normandy, France

    A worldwide unique experience in nuclear

  • 5A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    The Starting Point

    End of 1970s in France: first PWRs(CP0) : Operation in Base Load (or smooth Load Follow) with A Mode

    Decision to raise the % nuclear power: PWRs need to comply with electrical grid constraints

    1975 to 1980

    AREVA conceived an innovative solution to meetchallenging grid constraints

  • 6A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Overview of the Grid Requirements

    The AREVA solution: capable of matchingthe daily electricity demand

  • 7A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Grid Requirements 1) Load Follow Transients

    Daily load follow program sent to Nuclear units

    SLOW TRANSIENTS ( 12 - 3 - 6 - 3)

    FAST TRANSIENTS (16 - 8)

    But … can be interruped by anINSTANTANEOUS RETURN to FULL POWER w/o NOTICE required by the Grid Owner

    100%

    70%

    50%

    30%

    6 h

    100%

    3 h 3 h

    70%

    100%

    3%/mn 5%/mn

    100%

    100% 100%3%/min

    50%

    30%

    3%/min

    Ramp up to full

    power at 5% per

    minute WITHOUT

    notice

  • 8A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Non predictable power variations: Frequency Control

    103

    101

    99

    97

    95

    93

    91

    89

    871 2 3 4 5 6 7 8 9 10 11 12

    Power

    Time (hours)

    Grid Requirements2) Frequency control

    Power matching to real time electricity demand

  • 9A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Outlines

    Requirements from the Grid

    Impact of Load Follow on French PWR Design

    Industrial Deployment of the Load Follow on French PWR

    Conclusions

  • 10A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Core Control Principles (1/2)

    Control Banks automatically move modifying core reactivity accord inglyand keeping the primary average temperature inside the allowed variationrange (→ reactor power and turbine/generator power are corre ctly balanced)

    Power variations requested by the grid

    Lead to SG outlet temperaturevariations and then to core inlet

    temperature modifications

    Opening/closing

    of the turbine inlet valves

    requierements Steam flow rate variations

  • 11A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Core Control Principles (2/2)

    Optimized control banks efficiencyfor better safetyand reactivity

  • 12A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Variations of the power level lead to variations of r eactivity� Nuclear feedbacks (Moderator + Doppler effects)

    � Xenon concentration variations

    Power

    Nuclear

    Feedbacks

    Xenon

    Reactivity

    Control

    Banks

    Dilution

    > 0< 0

    ACCORDING to the

    CORE CONTROL MODE

    Some Physics

  • 13A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Chronology of the Load Follow G” Mode “ Development

    • 1975-1980: Definition of the Load Follow G Mode core contro l principles

    Design of the core and NSSS control channels (I&C a spects)

    •1980-1985: Safety and Mechanical Analyses

    Equipment and Fuel Assembly Qualification in Tests Facilities

    On Site Load Follow G Mode Qualification Tests

    •1985-1990: Load Follow G Mode Industrialization

    •1995-2005: Development of the EPR core control mode: so-call ed “T Mode”

    1975 1980 1985 today

  • 14A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Impact on Core and Nuclear and Steam Supply System (NSSS) Control Channels (1/4)

    Core Control : creation of “Gray Mode” ( G Mode)

    Classical “Black” Rod Cluster Control Assembly (RCCA) design

    � 24 absorbing rods made of Silver/Indium/Cadmium, B4C or both

    � High anti-reactivity worth

    New “Gray” RCCA design

    � 8 absorbing rods made of Ag/In/Cd

    � 16 rods made of Stainless Steel

    � Low anti-reactivity worth

  • 15A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Impact on Core and NSSS Control Channels (2/4)

    Rod Cluster Control Assembly (RCCA) configuration

    � “Gray” control banks (G1, G2), followed by “black” control banks (N1, N2), drive load follow power transients

    � In addition to “Gray” control banks (G1, G2), “Black” control banks (N1, N2), are necessary for reaching zero power conditions

    � G1, G2, N1, N2 overlaps are managed to minimize axial power distribution distortions

    Core control principles

    � G1, G2, N1, N2 control the electrical power

    � One control bank (“R”) is dedicated to temperature control to

    • counter “nuclear feedbacks”• participate in the control of axial power distribution (axial-offset)

    1975 to 1980

  • 16A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Impact on Core and NSSS Control Channels (3/4)

    I&C Aspects

    �Need to switch to digital technology

    �Set points update via Memory Chips

    1975 to 1980

    The world’s first nuclear digital I&C technology!

  • 17A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Impact on Core and NSSS Control Channels (3/4)

    Control system modified to minimize mechanical cons traints

    on pipes and nozzles

    NSSS Systems

    � Pressurizer Surge Line � CVCS charging line nozzle

    1980 to 1985

    Major Safety improvements

  • 18A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Impact on Safety & Design Analyses

    Four additional shut down black control banks

    No new accident initiating events

    New core and NSSS initial conditions before possibl e accidents were analyzed

    Design File Transients were updated with the new eq uipment loadings

    The behavior and capacity of concerned systems were verified for the load follow transients: no design change

    Balance of Nuclear Island: no change

    1980 to 1985

  • 19A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Outlines

    Requirements from the Grid

    Impact of Load Follow on French PWR Design

    Industrial Deployment of the Load Follow on French PWR

    Conclusions

  • 20A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Equipment and Fuel Assembly Qualification Tests (1/2)

    Confirmation of resistance calculations in

    Tests Facilities:

    �Control Rod Drive Mechanisms• Tested in the CEA “Superbec Loop”

    �Core baffle: Fatigue resistance of bolting

    1980 to 1985

    Extensive testing on mock-ups led to industrialsolutions

  • 21A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Theoretical Approach�Fuel Assembly response to power variations

    Experimental Approach�Power ramps and cycling variations in CEA “CAP” reactor� International R&D programs

    In-reactor fuel surveillance program

    Fuel Cladding Rupture risk by Pellet Clad Interaction (PCI) �Above tasks showed this risk does not exist in Load Following

    Equipment and Fuel Assembly Qualification Tests (2/2)

    Extensive testing on mock-ups led to industrialsolutions

    1980 to 1985

  • 22A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    On Site Qualification Tests

    Tricastin Unit 3 First of A Kind

    � Load Follow control system co-existed with traditio nal control mode

    � Load Follow mode feasible both manually and automat ically

    Three successful testing Campaigns

    • October 1981 • November 1982• March 1983

    1980 to 1985

  • 23A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Industrialization of the Load Follow “G Mode”

    The 900 MW CPY power plants were designed as “bi-mod e units”

    The first units of TRICASTIN, GRAVELINES, DAMPIERRE,

    BLAYAIS (1, 2) were commissioned in base load

    They switched to load follow “G” Mode after Safety Au thorities

    authorization

    The other units started up directly in load follow “G ” mode

    No significant modifications implemented later on

    1985

  • 24A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    EPRTM Reactor and ATMEA1 Features

    Full automatic Control Mode including boration and d ilution

    Choice of operating strategy available to operator:

    � Instantaneous return to full power without notice c apability, or

    � Liquid effluents saving strategy (automatic countering of xenon effect by control banks)

    Best combination of “G mode” and German load follow practices = Advanced load follow “T Mode”

    1985 To today

  • 25A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Comparison of Core Control Modes

    1985 To today

    A Mode G Mode T Mode

    Control Channels Banks control Temperature

    G1,G2,N1,N2 Banks control Power

    R bank controls Temperature

    Banks control Temperature, Axial-Offset and Return to Full Power Capability

    Reactivity (Nuclear Feedbacks) Mainly Boron

    Control Banks (G1, … N2) Control Banks

    Xenon Boron Boron Control Banks or Boron

    according to the Operator Strategy

    Axial-Offset Control

    Manual by Operator (via Control Banks

    repositioning thanks to Boron Concentration

    manual Changes

    AO Distortions minimized thanks to G Mode Design Residual

    effects manually controlled by Operator

    Automatic by Control Banks

    Advantages Control Banks close to

    the top of the Core Nice for Neutronics

    Fits fast and Unscheduled Power

    Changes

    Fully Automatic including

    Boration/Dilution Full Return to Full

    Power Capability or Liquid Wastes saving

    Strategies

    Drawbacks

    Fits slow Power Changes only

    Limited by CVCS Capability

    Periodic Calibration of (G1,…N2) vs. Power Risk of CRDM Wear

    Secondary Side Interface

    More Complex

  • 26A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Outlines

    Requirements from the Grid

    Impact of Load Follow on French PWR Design

    Industrial Deployment of the Load Follow on French PWR

    Conclusions

  • 27A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    High Flexibility Level since Decades1975 to 1985

    Load follow license was obtained in 1983

    Frequency Control license was obtained in 1984

    48 Nuclear Units are presently operated in load following conditions according to the G Mode principles

    Thanks to AREVA’s innovative solutions, EDF is the first and only to perform load follow since 30 years!

  • 28A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Taishan 1-2 (T Mode)

    Daya Bay 1-2

    Ling Ao I 1-2

    Ling Ao II 3-4

    G Mode

    AREVA Load Follow experience in Foreign Countries

    L Mode

    1975 to today Worlwide Robust Experience

  • 29A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    Flexibility of the Energy Mix

    The T Mode is the fruit of a continuous development aiming at providing Utilities with the highest flexibility lev el� Capable to meet new grid requirements induced by re newable energies

    1975 to 1985……..Next

    AREVA anticipates future needs for both nuclear & renewable energies

  • 30A-M. CHOHO – SEVP Engineering & Projects - SFEN Youn g Generation, Paris, 21st Oct. 2013

    THANK YOU for YOUR ATTENTION!

    EPR Taishan 1&2EPR Flamanville 3

    EPR Olkiluoto 3