PDF-6.3 Safety Systems and Plant Tour

Embed Size (px)

Citation preview

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    1/20

    1

    A Look at Nuclear Scienceand Technology

    Larry Foulke

    Module 6.3

    Safety Systems and Plant Tour

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    2/20

    Nuclear Engineering Program

    PWR Control Rod

    Spider

    Image Source: See Note 1

    Full-Length Control Rods (inyellow) Mounted to Drives abovew/ Electromagnets

    Fuel rods (in red) contain UO2pellets inserted into a Zircaloy-4tube

    Spring clip grids provide supportfor the fuel rods in the fuelassembly

    Top and bottom nozzles of the fuelassembly control the coolant flowdistribution and serve as structuralelements

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    3/20

    Nuclear Engineering Program

    SCRAM / TRIP Full-Length Control Rods Mounted to Drives

    w/ Electromagnets

    Loss-of-Current Full Insertion

    PWR Protective System

    Trip / Protective Signals High Flux

    High Temperature

    High Pressure

    Manual

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    4/20

    Nuclear Engineering Program

    PWR (W)

    Plant

    Protection

    System

    Image Source: See Note 1

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    5/20

    Nuclear Engineering Program

    Trip Signals

    Redundancy

    Interlocks for Power Changes

    Reliability

    Avoid Spurious Trips

    Two-Out-of-Four Logic Same / Different Parameter

    Consistent w/ Need for Repair

    Fail-Safe Design

    PWR Protective System

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    6/20

    Nuclear Engineering Program

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    7/20Nuclear Engineering Program

    Engineered Safety Features (ESFs)

    Image Source: See Note 3

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    8/20Nuclear Engineering Program

    Engineered Safety Features

    Reactor Trip (RT) - 1st function

    Control rods

    Electromagnets / gravity insertion

    Protective system / redundant sensors

    Boric acid w/ emergency coolant injection

    Rods alone may not shut core down on reflood

    Boric acid concentration compensates for rodfailure

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    9/20Nuclear Engineering Program

    Engineered Safety Features

    Emergency core cooling (ECC) - 2ndfunction

    Break location

    Multiple loops

    Distributed insertion points

    Redundant / diverse

    High-pressure injection (HPI) Low-pressure injection (LPI)

    Accumulator

    On-site / off-site power supplies

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    10/20

    Nuclear Engineering Program

    Engineered Safety Features

    Post-accident heat removal (PAHR) - 3rdfunction Large break - Initially cool ECCS water

    Small break Forced circulation

    Single-phase natural circulation

    Two-phase natural circulation (reflux)

    Feed and bleed HPI/LPI water into core

    Steam discharged through Pzr PORV / safeties

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    11/20

    Nuclear Engineering Program

    Engineered Safety Features

    Post-accident radioactivity removal(PARR) - 4th function

    Charcoal adsorbers for fission products

    High-efficiency particulate air (HEPA) Filters

    Reactive coatings for passive removal ofhalides

    Containment water sprays

    wash reactive products from atmosphere

    Additives for pH control

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    12/20

    Nuclear Engineering Program

    Engineered Safety Features

    Containment integrity (CI) - 5th function

    Isolation valves on containment buildingpenetrations

    Automatic on overpressure signal

    Main steam line valve design for quick close

    Containment building

    Inner leak-tight steel liner

    Reinforced concrete shell

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    13/20

    Nuclear Engineering Program

    Engineered Safety Features

    Image Source: See Note 4

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    14/20

    Nuclear Engineering Program

    PWR Engineered Safety Features

    Image Source: See Note 3

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    15/20

    Nuclear Engineering Program

    Engineered Safety Features (ESFs)

    Image Source: See Note 3

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    16/20

    Nuclear Engineering Program

    Safety Design Principles

    Multiple barriers

    Defense-in-depth

    Protection / safety functions

    Redundancy

    Diversity

    Physical separation

    Fail-safe principle

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    17/20

    Nuclear Engineering Program

    Safety Design Principles

    Redundancy

    More than minimum number of components

    Design to tolerate component failure

    Diversity

    Protects against common-mode failure

    Control rods and boric acid injection

    Aux feed pumps - both electric and steam driven

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    18/20

    Nuclear Engineering Program

    Safety Design Principles

    Physical separation

    Protects against simultaneous loss

    Distance / physical barriers

    Combination redundant / diverse / separated

    Example: emergency electric power supply

    Diesel generators

    Multiple ties to off-site electrical grid Storage battery systems

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    19/20

    Nuclear Engineering Program

    Safety Design Principles

    Fail-safe principle

    Components / systems automatically into safestcondition w/ failure or power loss

    Examples: PWR rods - electromagnetic and gravity

    BWR rods - solenoid / gas pressure

  • 7/27/2019 PDF-6.3 Safety Systems and Plant Tour

    20/20

    1. Reprinted with permission from Westinghouse. Course:The Westinghouse Pressurized Water Reactor NuclearPower Plant (The Masche Book).

    2. Reprinted with permission from Nuclear Engineering

    International UK. Source: World Nuclear IndustryHandbook 2013

    3. Adapted with permission from the American NuclearSociety. Nuclear Engineering Theory and Technology ofCommercial Nuclear Powerby Ronald Allen Knief, 2nd

    Edition. Copyright 2008 by the American Nuclear Society,La Grange Park, Illinois. Figure 14-1 (slides 7 and 15) and14-2 (slide 14).

    4. Reprinted with permission from Nuclear Energy Institute.http://www.nei.org/corporatesite/media/filefolder/containm

    ent wall construction.jpg

    Image Source Notes

    http://www.nei.org/corporatesite/media/filefolder/containment_wall_construction.jpghttp://www.nei.org/corporatesite/media/filefolder/containment_wall_construction.jpghttp://www.nei.org/corporatesite/media/filefolder/containment_wall_construction.jpghttp://www.nei.org/corporatesite/media/filefolder/containment_wall_construction.jpg