Industrial Energy Management Chapter 4 : Nuclear Power Plants
Transcript of Industrial Energy Management Chapter 4 : Nuclear Power Plants
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Industrial Energy Management
Chapter 4 : Nuclear Power Plants
Jun.-Prof. Benoît Fond, G-10/R-119
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Intro
April 2007 : 30 countries operate 449 nuclear
reactors for electricity generation. 60 new reactors
under construction
11 % of world electricity production is nuclear energy
(40% coal, 22.2% gas, 16.5 % Hydro)
Nuclear Power worldwide
Billion kWh as of 2016
Source:
nuclear energy institute
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Layout
1. Physical principles of nuclear power
• Atomic structure and radioactivity
• Fission reactions
• Criticality
2. Topology of nuclear power plants
• Classification
• Pressurized water reactors
• Boiling water reactors
• Fast neutron reactors
3. Nuclear Waste treatment
4. Risks
Nuclear Power plants
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Atom (10-10m): Core (10-15m) + electron cloud
Binding energy : Due to forced between particles, forming atoms from
constituent protons, neutrons, and electron releases energy. Mass is
turned in energy -> Mass defect
The mass of the atom is smaller than the mass of separated particles :
E=mc2
Atomic structure and radioactivity
Physical principles of nuclear power
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Physical principles of nuclear power
A(mass number)=Z(atomic
number)+N(number of neutron)
From mass we can calculate mass
defect.
Uranium has two natural isotopes or nuclides:238U (99.3%) and 235U (0.7%)Table of chemical element
Same Z
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Physical principles of nuclear power
Valley of Stability
Spontaneous radiative decay :
• Alpha : 𝑍𝐴𝑋 → 𝑍−2
𝐴−4𝑌 + 24𝐻𝑒
• Beta+ : 𝑍𝐴𝑋 → 𝑍−1
𝐴𝑌 + 𝑒− + തν
• Beta- : 𝑍𝐴𝑋 → 𝑍+1
𝐴𝑌 + 𝑒+ + ν
𝑁 𝑡 = 𝑁0𝑒−𝑡/𝜏 = 𝑁02
−𝑡/𝑡1/2
Half-life 238U: 4,5 109 years235U: 7,2 108 years14C: 5,7 103 years
Radioactivity
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Physical principles of nuclear power
Binding energy per nucleon
Fission reaction :
An heavy nuclide split into two smaller
ones
~0.85 MeV per neutron -> 200 MeV
per nuclide
Chemical reaction e.g. C oxidation ->
a few eV
Fusion reaction :
Two light nuclide form a bigger one
e.g. 2H + 3H -> 4He + 1n 17.6 MeV
Fission
Fusion
Fuel Energy per kg of
fuel
235U (fission) 23.000.000 kWh
2H + 3H (fusion) 96.000.000 kWh
C 9 kWh
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Physical principle of Nuclear Power
1n + 235U -> X + Y + 2,4 n + …
Reaction needs “excitation energy” : fission
energy barrier (for deformation prior to fission)
kinetic energy of n + binding energy of n to
nuclide neutron
Binding energy of n to 235U is much higher and 238U rarely fissions
Energy release 200 MeV
82% kinetic energy of X and Y
11% neutron, beta, gamma radiation
7 % later radiative decay
Neutron emission
Prompt neutrons (99%, immediately)
Delayed neutrons (0.7%, during later radiative
decay)
Net neutron growth -> Possibility of chain
reaction -> Bomb
Fission reactions
1%
Source : Energie,
electricité et
nucléaire, G.
Naudet and P.
Reuss, EDP
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• Every fission produces on average v
(rapid) neutron
• Every emitted neutron has probability w
to cause fission of heavy nuclide
-> Multiplicity factor 𝑘 = 𝑤 × 𝑣 effective
neutron multiplication factor
From N fissions, kN new fissions can be
obtained
k<1 subcritical : the reactor stops
k=1 critical : steady state – normal operation
k>1 supercritical : reaction amplifies –
reactor start or bomb
Criticality
Physical principle of Nuclear Power
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Physical principles of nuclear reactors
v is fixed, so we must control w probability of
emitted (rapid) neutron to trigger new fissions
What happens to a (rapid) emitted neutron ?
• It collides with another atom
(thermalisation) and becomes slower
• It is absorbed by another nuclide :
• Fertile capture : Fission (235U)
• Sterile capture : No Fission (238U)
• It leaves the reactor
With 235U, the probability of capture of thermal
neutron is high
• We must allow thermalisation. To slow
down neutron, a moderator material is
used. It must be have light nuclide for
efficient diffusion, but not capture neutron
How to change k ?
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Physical principles of nuclear reactors
Size of the reactor (leak)
Poisons and absorbers :
Indium and Cadmium on control rods to capture neutron.
Boric acid (liquid)
Fission product poisons : 135Xe and 149Sm
Consumable poison : B, Gd
Temperature : negative effect of temperature on criticality is needed for
reactor safety
Doppler effect on 238U : increase capture (+)
Water dilation : decrease scattering (-) and thermal neutron capture (+)
How to change k ?
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For prompt neutron, average dt = 25 microseconds. Rate : 40000/s
If k=1.0001, after 1s, kn=55 (+ 5500%)
Some neutrons (0.7%) are emitted from fission products after radioactive
decay. Decay takes 11 s
So for 1000 neutrons, 7 have a dt of 11 s and 993 a dt of 25 microsecond, so
on average, dt is 0,08 s
If k=1.0001, n=12.5 after 1s, kn= 1,0013 (+0.13%)
Must slower response.
The role of delayed neutron
Physical principles of nuclear reactors
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Topology of nuclear reactors
Light nuclides for efficient deceleration
Low probability of neutron capture. High density to reduce deceleration
distance.
Normal water : Very good moderator (+++), but high capturing rate.
Requires enriched uranium -> Mostly used. Pressurized water reactor (66%),
Boiling water reactors (23%, e.g. Fukushima)
Heavy water (2H2O) : Good moderator (++), and low capturing rate ->allow
natural uranium -> CADUX Heavy water reactor (5% Canada)
Graphite : Average moderator (+), and low capturing rate ->allow natural
uranium
Cheap and high thermal properties. -> 6% UNGG (France), Magnox (UK),
RBMK (USSR, Tchernobyl)
Moderator
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Combustible: Natural Uranium, Enriched Uranium, Plutonium, MOX (Plutonium
and natural Uranium).
Moderator Medium : Water, Heavy water (2H2O), Graphite, None (Rapid neutrons)
Heat transfer Medium : Pressurized water, Boiling water, Heavy water, CO2, He
Cladding material
Absorbers
Main elements of nuclear reactors
Topology of nuclear reactors
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Topology of nuclear reactors
The Fermi Pile (1942, Chicago)
Natural Uranium and Graphite
Geiger counter
Reads neutron flux Moves control rod
Fermi & Co
reads Geiger counter
Safety :
Heavy absorbing bar
Cadmium Salt solution
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• Enriched Uranium (3-4% 235U) as Fuel
• Water as moderator
• Water as working fluid
• 3 Water Loops
• Primary circuit, 150 bar,
~280-320°C, liquid only
Moderator and rod
cooling
• Working fluid, 70 bar
~280° C (Water/steam)
• Condenser cooling
water
Pressurised water reactor
Topology of nuclear reactors
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Pressurised water reactor
Topology of nuclear reactors
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Pressurised water reactor
Topology of nuclear reactors
Each fuel rod is sheathed with Zircalloy
Moderator flows in between
Empty rods for control
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Pressurised water reactor components
Reactor vessel primary cooling pump boilerPrimary water loop
Topology of nuclear reactors
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Boiling water reactors
Two water loops only. Primary water at 70 bar
Boiling and moisture separation in reactor
Topology of nuclear reactors
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Topology of nuclear reactors
Enriched Uranium Oxide (~2-3%)
Control rod at bottom
Steam liquid cyclone separator at top
Advantage :
Simpler (only two loops)
Disadvantages :
Bigger reactor (less dense)
Radioprotection : Water is radioactive after
neutron capture (16N) so turbine casing must be
protected from radiation
Boiling water reactors
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Topology of nuclear reactors
Heavy water reactors
Moderator (Heavy water) is not pressurized, but circulated to prevent
heating
Working fluid (Heavy water) flows around rods in pressure tubes
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Topology of nuclear reactors
Heavy water reactors
Little neutron capture -> run
on natural Uranium
No pressure on reactor pool
-> light construction
Mainly developed by
Canada
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Neutron capture by 238U produces plutonium after beta - radiation
239Pu is fissile upon capture of rapid neutron, and produces more neutrons.
Neutron excess in chain reactions
->Rapid neutron reactor without moderator, with 239Pu/238U as fuel
Pu fission -> emission of rapid neutron:
-> Captured by 238U-> produces Pu : Breed more Pu that it consumes
-> Captured by 239Pu-> more fission
Liquid sodium used as heat carrier, little neutron diffusion, little neutron
capture, large temperature range as liquid
Fast neutron reactors (breeder)
Topology of nuclear reactors
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Topology of nuclear reactors
Fast neutron reactors (breeder)
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Nuclear fuel cycle and waste
Fuel cycle and waste
Specificities :
• Very high energy density, muss smaller mass to handle
• Possibility for regeneration in breeder reactor
• Fuel still emit heat after use for years due to radioactive decay of fission
products
• Fuel is not fully exhausted after use in reactor.
Nuclear Fuel production:
Uranium Ore mining
Chemical reaction -> UF6 -> Separation 235U and 238U for enrichment
Uranium Oxide Formation or MOX (Enriched Uranium and Platinum)
Yearly consumption ~70,000 tons, Reserves ~50 years for regular 3% 235U
fuel. Outlook : Breeder and Thorium
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• Fuel waste
retreatment
possible (239Pt, 238U and 235U)
• Highly radioactive
wastes
• Gamma and
neutron radiation
are most
dangerous
Waste
Fuel cycle and waste
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Risk
Dissemination of radioactive products
Exposure to radioactivity on plant components
Accidents :
• Core Meltdown (Fukushima and Three Miles Island), cooling issues after
emergency shutdown, plus valve failures or H2 explosion ->dissemination
• Supercritical reaction (Tchernobil) - > Explosion
Risk
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References
R. L. Murray, Nuclear Energy : An Introduction to the Concepts,
Systems, and Applications of Nuclear Processes, BH
Textbooks