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WP4 PLANT OPERATION, INSTRUMENTATION, CONTROL AND PROTECTION SYSTEM DESIGN

WP4 PLANT OPERATION, INSTRUMENTATION, CONTROL AND PROTECTION SYSTEM DESIGN. LEADER. F. Rivero May 9th 2013, Genoa. Deliverables. M08 → Conceptual definition of the control and protection functions and its architecture → M34 → January 2013. 2010. 2011. 2012. Schedule. 2013.

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WP4 PLANT OPERATION, INSTRUMENTATION, CONTROL AND PROTECTION SYSTEM DESIGN

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  1. WP4PLANT OPERATION, INSTRUMENTATION, CONTROL AND PROTECTION SYSTEM DESIGN LEADER F. Rivero May 9th 2013, Genoa

  2. Deliverables M08→ Conceptual definition of the control and protection functions and its architecture →M34 → January 2013

  3. 2010 2011 2012 Schedule 2013 • Task 4-2 → DEL06 “State of the art Instrumentation and Control Survey” • Task 4-1 → DEL14 “Normal, transient and accidental operational modes: control and protection functions identification” • Task 4-3 → DEL20 “Instrumentation Specifications” • Task 4-4 → DEL21 “Preliminary definition of the control architecture”

  4. WP4 Work Program • Deliverables • Tasks responsible • Schedule • Documents indexes • Chapters responsible • Chapters participants • Input data

  5. Task 4-1: Normal, transient and accidental operational modes: functions identification D14 Normal, transient and accidental operational modes: control and protection functions identification Revision 1 / Final (October 2012) Objectives Definition of the operational modes and parameters or functions to be controlled Schedule: November 2012 Activities Plant operation procedures involving both primary and secondary systems Perform the conceptual design of the plant control and protection systems CIRTEN, EA, SCKCEN 5

  6. Identification of functions for plant control and protection • Protection functions: • Basically: automatic and manual initiation of reactor trip (RT) and engineered safety features (ESFs) • Post-accident functions: • Basically: automatic and manual control of the ESFs necessary to reach a safe shutdown state during the first 24 h from the beginning of the event • Control and limitation functions • Control of lead temperature at core outlet by means of CRs • Limitation of reactor power • Control of lead temperature at SG outlet • Control of feedwater temperature • Control of oxygen concentration in the coolant • Control of turbine speed • Other I&C funtions • Severe accident functions: Severe accident monitoring • Risk reduction functions: Mitigation of ATWS and software common cause failures by means of a diverse actuation of reactor trip • Management of priority and actuation control functions: Management of priority of actuator commands, Monitoring and protection of the actuators, Interlocks, Etc. • HMI functions: Alarm display and processing functions, Data archiving and processing functions 6

  7. Basic structure of I&C architecture • For each function • Safety classification according to EUR • Identification of plant parameters to be measured • Define interventions of the I&C systems to counteract • Definition of a digital I&C architecture organized on 4 levels • Level 0: Process Interface Level (Sensors and actuators) • Level 1: System Automation Level (Closed loop and open loop controls) • Level 2: Unit Supervision and Control Level (Data processing for HMI) • Level 3: Site Management Level (no direct influence on plant behaviour) 7

  8. Basic structure of I&C architecture 8

  9. Task 4-2: State of the art I&C survey • D06 State of the art I&C Survey • Revision 1 (December 2012) • Objectives • Evaluate the applicability of available I&C equipment to the LFR operational needs • Identify future R&D needs in the field of I&C • Activities • Collect information in relation with the lead technology • Identify needs (instruments and control devices) • Contact companies • EA, SCKCEN

  10. Core monitoring instrumentation survey • Main parameter related to core: neutron flux (+ change rate) • Low-level neutron flux monitoring during critical approach and start-up phase • Fast neutron flux change measurement (anywhere) for trip signal in case of sudden reactivity increase • In-core neutron detection at various positions for neutron flux mapping (radially – axially) • Fission chambers. Temperature • mostly specified up to 250°C, 300°C, 350° • models exist up to 500-600°C (e.g. Photonis CFUE22-32-42-43, CFUC06-07, used in PHENIX, SPX) • Self-powered neutron detectors • Typically applied for thermal neutron detection • Thermocoax, KWD Nuclear Instrum. AB, Mirion Technol. – IST,… 10

  11. Primary coolant instrumentation survey • Temperature • Thermocouple protected with a thermowell resistant to corrosion • Similar experiences in metallurgic sector or molten aluminum • Thermo-Couple Products Co. (Marsh Bellofram Group) • Pyrosales Pty Ltd • Termo Kinectics • Level • Radar to avoid physical contact with lead • Support high temperature • Emerson / Aplein Ingenieros. Model: TankRadar Pro Steel • Metallurgical applications and molten salts • Used to measure level in molten salts • Temperature at antenna: up to 1000 ºC • Vega, Model: Vegapuls 68, • Endress Hauser. Model: FMR230 M • MBA instruments. Model: MBA400 11

  12. Primary coolant instrumentation survey • Pressure • Capacitive transmitter with a seal • Used in hot temperature or highly corrosive processes • Temperature limitation due to fill fluid • Fill fluid: Sodium-potassium alloy (NaK), high temperature up to 700 - 800 ºC • Creative Engineers Inc, MTI Instruments • Flow • Elbow flow meter in pumps output • Differential pressure transmitter connected to the elbow with a diaphragm seal filled with Sodium-potassium alloy (NaK) • Creative Engineers Inc, MTI Instruments • Oxygen Analyzers • Electrochemical cells of YSZ (Yttria Stabilized Zirconia) • Excellent oxidation/corrosion resistance • High temperature • No COTS available 12

  13. Task 4-3: Instrumentation Specification • D20 - Instrumentation specifications • Revisio 0 (December 2012) • Objectives • Instrument Specifications • Activities • Prepare the design specification of the instruments and control devices • Schedule: January 2013 • EA, ENEA, INR, SCKCEN

  14. Core and Primary coolant instrumentation Fuel Assembly Safety Rods Control Rods Dumy Element In-core Detector (3 elevations) Close-to-core Detector (top to bottom) • Ex-core / In-core neutron flux detector configuration • Technical and design requirements for Primary coolant instrumentation • Temperature • Pressure • Level • Flow • Oxygen concentration • Steam concentration in cover gas • Qualification requirements following IEC 60780 14

  15. Secondary Coolant. Pressure Steam generator output (1, 2...8) HPT input LPT input By-pass valve input Condensate pumps output (1 & 2) Steam generator input (1, 2…8) Deareator Feedwater pumps output (1 & 2) 15

  16. Secondary Coolant. Temperature Steam generator output (1, 2...8) Auxiliary heater input By-pass valve output Main steam line Steam generator input (1, 2…8) Feedwater line Deareator input bypass line 16

  17. Secondary Coolant. Flow Attemperation valve input Feedwater line 17

  18. Secondary Coolant. Level Deareator Condenser Preheaters (1, 2. . .6) FWTC Heater 18

  19. Radiation Monitoring Containment air Main Control Room intake air • Fuel Intermediate Storage • Equipment Hot Cell • Spent Fuel Hot Cell • Spent Fuel Storage Building Plant vent exhaust • Area Radiation Monitoring Process Radiation Monitoring

  20. Task 4-4: Preliminary definition of the Control Architecture • D21 - Preliminary definition of the Control Architecture (Milestone M08) • Revision 0 (January 2013) • Objectives • Define the conceptual European Lead Cooled Fast Reactor control and operation philosophy to maintain the reactor in operable and safe conditions • Activities • Define the control architecture to perform • Schedule: January 2013 • ANSALDO, CIRTEN, EA, INR, SCKCEN

  21. Plant model

  22. Full power control scheme

  23. Reactor start-up and coordination with the full power mode

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