Wp4 plant operation instrumentation control and protection system design
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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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Wp4 plant operation instrumentation control and protection system design

WP4PLANT OPERATION, INSTRUMENTATION, CONTROL AND PROTECTION SYSTEM DESIGN

LEADER

F. Rivero

May 9th 2013, Genoa


Deliverables

Deliverables

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


Schedule

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”


Wp4 work program

WP4 Work Program

  • Deliverables

  • Tasks responsible

  • Schedule

  • Documents indexes

  • Chapters responsible

  • Chapters participants

  • Input data


Task 4 1 normal transient and accidental operational modes functions identification

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


Identification of functions for plant control and protection

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


Basic structure of i c architecture

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


Basic structure of i c architecture1

Basic structure of I&C architecture

8


Task 4 2 state of the art i c survey

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


Core monitoring instrumentation survey

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


Primary coolant instrumentation survey

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


Primary coolant instrumentation survey1

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


Task 4 3 instrumentation specification

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


Core and primary coolant instrumentation

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


Secondary coolant pressure

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


Secondary coolant temperature

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


Secondary coolant flow

Secondary Coolant. Flow

Attemperation

valve input

Feedwater line

17


Secondary coolant level

Secondary Coolant. Level

Deareator

Condenser

Preheaters (1, 2. . .6)

FWTC Heater

18


Radiation monitoring

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


Task 4 4 preliminary definition of the control architecture

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


Plant model

Plant model


Full power control scheme

Full power control scheme


Reactor start up and coordination with the full power mode

Reactor start-up and coordination with the full power mode


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