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Nucleonic Measurement Integral System ObsolescenceFree

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Title: Nucleonic Measurement Integral System ObsolescenceFree


1
Nucleonic Measurement Integral System
Obsolescence-Free
2
Scope of Presentation
  • System Presentation
  • Design Evolution
  • How to guarantee Obsolescence-Free
  • How to increment Reliability
  • System Life Cycle
  • Qualification Process

3
Nucleonic Instrumentation Channels
  • Source/Start-up channel
  • Intermediate/Power channel
  • Wide Auto Range Linear channel
  • Gamma Linear Channel
  • SPND Linear Channel

4
Nucleonic Instrumentation Channel Ranges
5
Design Evolution
  • Evolutionary design from the early 1970s
  • Technologic Evolution Phases
  • Originally Based on Discrete Technology
  • Incorporation of LSI
  • Incorporation of Integrated Analogue Technology
  • Incorporation of ASIC/FPGA

6
Design Evolution
  • New Features and Functions
  • Add-in Simulators
  • Auto-testing Capability
  • Discrete Digital and Analogue Interfaces
  • Remote configuration capacity
  • Digital communication Interfaces

7
Key for Obsolescence Free
Simplified Hierarchical Structure of a System
8
Key for Obsolescence Free
  • Within this hierarchical structure and in case of
    In-House Designs,
  • Critical elements are the parts, generally
    subject to third party suppliers,
  • Without control in
  • Availability
  • Validity
  • Possible Obsolescence

9
Key for Obsolescence Free
  • Design Evolution based on
  • Well proven technology
  • Second and Third Party Provision Sources of parts
  • Stockpiling of critical parts

10
Key for Obsolescence Free
  • In this way it is possible to assure
  • Validity of designs
  • Improvement/enhancement of features
  • Compatibility of the components backwards

11
How to increment Reliability
  • Design Premises,
  • From a safety standpoint
  • Reliability
  • Simple failure criterion
  • Fail Safe
  • Fault Tolerant
  • Control over Common-Cause Failures
  • Qualification for use in nuclear installations,
    particularly in reactors
  • High Quality
  • Robustness

12
How to increment Reliability
  • Design Premises,
  • From a performance standpoint
  • Accuracy
  • Precision
  • Availability
  • High response speed
  • Long life cycle
  • Short and long term stability
  • Capability to communicate with other plant
    systems for the transmission of parameters
    measured and processed by the system

13
How to increment Reliability
  • How to achieve these design premises

14
How to increment Reliability
  • How to achieve these design premises

15
System Life Cycle
16
System Life Cycle
  • The life cycle of the system, divided into their
    different stages or phases, is carefully
    conducted, while the necessary design
    modifications are duly supervised through
    standard methods.
  • All activities are organized within the System
    Life Cycle with the implementation of a program
    that includes the following plans
  • Project Management Plan
  • Design/Development Plan
  • Verification Validation Plan
  • Configuration Management Plan
  • Quality Assurance Plan

17
Qualification Process
  • In turn, a component qualification plan ensures
    the safe application of the systems in nuclear
    installations. This plan is based on the IEEE
    qualification standard for the Nuclear
    Engineering area.

18
Qualification Process
  • The qualification plan is adjusted to the type of
    system from a safety standpoint, following IAEAs
    classification

19
Qualification Process
20
Qualification Process
  • Hence, the qualification plans include the
    following activities and application of standards
    in accordance with the system class

21
Qualification Process
  • Safety Systems
  • IEEE 1E applicable standards (IEEE 323 and 344)
  • FMEA (IEEE 352)
  • EMC/EMI-type tests / Compliance Certification
  • IEEE 7.4.3.2, IEEE/ANSI Standard Application
    Criteria for Programmable Digital Computer
    Systems in Safety Systems of Nuclear Power
    Generating Stations

22
Qualification Process
  • Safety-Related Systems
  • Type Test or Conformance Certificates
  • EMC/EMI Compliance Certification
  • Seismic and Vibration Compliance Certification
  • IEEE 7.4.3.2, IEEE/ANSI Standard Application
    Criteria for Programmable Digital Computer
    Systems in Safety Systems of Nuclear Power
    Generating Stations

23
Qualification Process
  • The integral nucleonic measurement system is
    specifically classified as Safety System and it
    is qualified as Class 1E component, following the
    methodology recommended by the standard IEEE 323.

24
Qualification Process
25
Nucleonic Channels
  • The following is the full measurement chain line

  • Source or Start-up channel
  • Intermediate channel (IC)
  • Power channel (IC or CIC)
  • Wide Range log channel
  • Wide Linear auto-range channel (mainly used for
    automatic reactor power control)
  • Gamma measurement channel (may be used as global
    reactor power corrector through the 16N measuring
    method)
  • SPND channel, (mainly used for in-core
    instrumentation)

26
Nucleonic Channels
  • These chains generally respond to the same
    configuration, with special features given by the
    characteristics of the sensor and the measuring
    principle.

27
Nucleonic Channels
  • Basic general chain configuration Signal
    detection
  • Detector
  • Initial signal processing
  • Pulse amplifier
  • Charge pre-amplifier
  • Pre-amplification
  • Processing
  • Logarithmic or linear amplifier (with or without
    self-range capacity)
  • Quadratic amplifier (Campbellian mode)
  • Period or Rate extractor
  • Rate meter

28
Nucleonic Channels
  • Basic general chain configuration Signal
    detection
  • Auxiliary elements
  • High voltage power supply units
  • Low voltage power supply
  • Communication units
  • Discrete signal electric isolation units
  • Digital signals
  • Analogue signals
  • Digital communication units (Field Buses)
  • Physical support for the units
  • Cabinet mechanical specifications
  • Input-output connector specifications

29
Nucleonic Channels
  • SOURCE/START-UP CHANNEL
  • The Source/Start-Up channel is used to monitor
    core neutron flux from the earliest stages of
    reactor operation (neutron source level), up to 5
    measurement decades.

30
Nucleonic Channels
  • INTERMEDIATE AND POWER CHANNEL
  • The Intermediate and Power Channel is used to
    monitor core neutron flux over more than 6
    decades to cover the reactors power operation
    range.

31
Nucleonic Channels
  • WIDE RANGE CHANNEL
  • The Wide Range Channel is used to monitor the
    reactors neutron flux from intermediate level to
    125 of full Wide Range level, and is capable of
    feeding the neutron flux evolution to the Reactor
    Power Regulation System to allow automatic
    reactor power control.

32
Nucleonic Channels
  • GAMMA LINEAR CHANNEL
  • A Gamma linear channel is used for gamma flux
    measurement.

33
Nucleonic Channels
  • SELF POWERED NEUTRON DETECTOR UNIT SPND
  • The Self-Powered Neutron Detector Unit is used to
    monitor the reactors neutron flux over more than
    7 decades.
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