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Nuclear Fundamentals Part II

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Nuclear. Fundamentals Part II. Harnessing the. Power of the Atom. Topics To Cover ... to allow for steam space (NO other part of primary at saturation conditions) ... – PowerPoint PPT presentation

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Title: Nuclear Fundamentals Part II


1
Nuclear Fundamentals Part II
  • Harnessing the
  • Power of the Atom

2
Topics To Cover
  • Components of Reactor
  • Reactor Core
  • Reactor Vessel
  • Supporting Components
  • Pressurizer (Pzr)
  • Reactor Coolant Pumps (RCPs)
  • Steam Generators (S/Gs)
  • Shielding
  • Control of Reactor

3
Goal Determine Functions
4
Primary Loop
5
Core Assembly
  • Fuel Assembly stores, supports, and isolates
    fuel
  • Plate UO2 clad with Zr metal very thin to allow
    for effective heat transfer
  • Sub-Assembly group of edge-welded plates w/
    fluid channels between
  • Cell group of several sub-assemblies w/ control
    rod fluid in center
  • Core collection of cells

6
Core Assembly
  • Primary Coolant removes heat produced by fission
    in fuel
  • Naval reactors use water (effective, easily
    replaceable, does not radiate)
  • Typical outlet temp 500 oF
  • Typical inlet temp 450 oF
  • Typical temp w/in core ?

7
Pressure Vessel
  • Purpose provides structural support for Rx core
    directs flow of coolant thru core
  • Closure Head removable cover on top of pressure
    vessel
  • Closure bolts hold down
  • Uses seal to prevent leakage
  • Houses Control Rod Drive Mechanisms (CRDM)

8
Control Rods and CRDMs
  • Electronically position control rods
  • Supported by closure head
  • Control Rod
  • Considered neutron leakage
  • Coarse Adjust for Reactor Power
  • Hafnium
  • High sa (sa sc sf)
  • High sc
  • Low sf

9
Control Rods
  • Shutdown with all rods lowered, Rx cannot go
    critical
  • Startup lift control rods to reduce leakage
    until Rx is critical continue to lift until temp
    of moderator reacts to rod height changes -gt let
    moderator control power
  • SCRAM quick shutdown of Rx drop rods to bottom
    vice electronically lower (SuperCritical Reactor
    Ax Man)

10
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11
Pressurizer (Pzr)
  • Purpose maintains primary coolant in subcooled
    state (prevent boiling) and provides surge volume
    for power transients
  • Operates at saturation conditions to allow for
    steam space (NO other part of primary at
    saturation conditions)
  • Uses electric heaters/spray to maintain high temp
    pressure

12
Pressurizer (Pzr)
  • If Pzr not used
  • Boiling in reactor core reduces ability to remove
    heat (mass flow rate and heat capacity reduced)
  • Boiling in pumps causes cavitation -gt loss of
    flow through core

13
Reactor Coolant Pumps (RCP)
  • RCP circulates primary coolant through the core
  • Multiple RCPs for redundancy
  • Hermetically sealed (no leakage)

14
Steam Generator (S/G)
  • S/G acts as heat sink for reactor and produces
    steam for MS system
  • Shell and tube heat exchanger
  • Moisture Separators
  • Non-nuclear side called the Secondary

15
Shielding
  • Serves two purposes
  • Reduce radiation outside reactor compartment to
    protect personnel
  • Reduce radiation inside reactor compartment to
    protect instruments/equipment

16
Shielding
  • All contained within RC to minimize radiation
  • Pressure Vessel Core
  • Pressurizer (Pzr)
  • Reactor Coolant Pumps (RCPs)
  • Steam Generators (S/Gs)

17
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18
Controlling Fission
  • To control fission, must control slowing down
    /thermalizing of ns (some leakage) -gt control
    rods and moderator used
  • Moderator
  • Substance used to slow down ns by elastic
    collisions
  • Qualities of a Good Moderator
  • high ss (scattering cross-section)
  • low sa (absorption cross-section)
  • atomic mass close to neutron (ie hydrogen)

19
Controlling Fission
  • Navy uses water as moderator (H2O)
  • Temperature of water determines amount of
    interaction
  • Temp water becomes more dense
    causes more collisions ns travel shorter
    distance to get thermalized less chance of
    leakage more fission power

20
Reactor Plant Control
  • Core reactivity/power is inversely proportional
    to moderator temperature (negative temperature
    coefficient)
  • Operating AA1/3 -gt AAIII Ordered
  • Open throttles -gt Steam demand -gt Tc
  • Tave -gt density moderator -gt greater
    chance neutrons will collide with H2O

21
Reactor Control
  • Higher prob. that neutron will thermalize and
    cause fission -gt fission rate -gt Rx power
  • Th -gt Tave -gt density moderator -gt more
    chance of fast leakage
  • Lower prob. that neutron will thermalize -gt
    fission rate -gt reactor power
  • Tave returns to steady state

22
Reactor Control
  • Overall, REACTOR POWER FOLLOWS STEAM DEMAND
  • While Tave will remain roughly constant from
    steady-state to steady-state, Th and Tc will
    change depending on steam demand

23
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