core group non-pwr/bwr reactors - mit …core group non-pwr/bwr reactors lecture 1 22.033/22.33 –...
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Core Group
Non-PWR/BWR Reactors
Lecture 122.033/22.33 Nuclear Engineering Design Project
Sep. 12, 2011
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 1
http:22.033/22.33http:22.033/22.33
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Main Parameters to Consider
Coolant Moderator Thermo. cycle
& TTin out Neutron spectrum Materials Power density
MIT Dept. of Nuclear Science and Engineering 22.033/22.33 Nuclear Design Course
Special features Commercial
readiness Safety
(active/passive) Efficiency Fuel
Dr. Michael P. Short, 2011 Page 2
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Relative Scales for Parameters
Outlet Temperature Low: 700C Very high quality process heat, maximum flexibility
Power level Low: 100-300MWe Medium: 300-750MWe High: >750MWe
Feasibility Low: Test reactors only Medium: Few operated
plants, some designs High: Operating plants,
mature designs
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 3
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Acronyms!
LBEFR CANDU RBMK
LBE LFR NNFR IFR AGR PHWR
GFR MSRVHTR SCWR SFR PBMR NaK
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 4
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Gas Cooled Reactors
More acronyms: -NU (natural uranium) -(L,M,H)EU (low, medium, high) enriched
uranium
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 5
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AGR (Advanced Gas-cooled Reactor)
Coolant: CO2 Tout: Med-high
Fuel: LEU Moderator: Graphite Power level: Med. Power density: Low
(Why?) Feasibility: High
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 6
Wikipedia User: MesserWoland. License CC BY-SA. This content is excluded from ourCreative Commons license. For more information, see http://ocw.mit.edu/fairuse.
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AGR Special Features, Peculiarities
Capable of on-load fueling (or part-load)
Graphite moderator must be cooled due to oxidation in CO2
Courtesy of Sellafield Ltd. Used with permission.
Windscale Prototype AGRImage source: http://www.sellafieldsites.com/
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 7
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PBMR(Pebble Bed Modular Reactor)
Coolant: Helium Tout: High
Fuel: LEU - MEU Moderator: Graphite Power level: Low Med. Power density: Low Feasibility: Low Med.
Public domain image.
Adapted from: Wikimedia Commons
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 8
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PBMR Special Features, Peculiarities
Continuous fuel cycle Pebble fuel (not rods) Pebbles act as built-in
disposal methods Very passive safety
systems (nat. circ.) Unknowns: material
concerns (fission products), stresses
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 9
Fuel Element Design for PBMR
5mm Graphite Layer
Coated Particles Imbedded in Graphite Matrix
Diameter 60 mmPyrolytic CarbonFuel Sphere
Silicon Carbite Barrier Coating
Inner Pyrolytic CarbonHalf Section
Porous Carbon Buffer
Diameter 0,92mmCoated Particle
Diameter 0,5mmUranium Dioxide
Fuel
Image by MIT OpenCourseWare.
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VHTR (Very High Temperature Reactor)
Coolant: Helium, molten salt Tout: High (very!)
Fuel: LEU - MEU Moderator: Graphite Power level: Low Power density: Low or high
Courtesy of Idaho National Laboratory. Used with permission. Feasibility: Low Med.
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 10
Coolant: Helium, molten salt
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VHTR Special Features, Peculiarities
High Tout opens up all doors to hydrogen
Significant high-T materials concerns
Molten salt variety can be more corrosive
Single phase coolant TRISO particles, ups &
downs MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 11
Diameter 60 mmFuel Sphere
Half Section
Diameter 0,92mm
Diameter 0,5mmCoated Particle
FuelUranium Dioxide
5mm Graphite Layer
Coated Particles Imbedded in Graphite Matrix
Pyrolytic CarbonSilicon Carbite Barrier Coating
Inner Pyrolytic Carbon
Porous Carbon Buffer
Fuel Element Design for PBMR
Image by MIT OpenCourseWare.
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Water Cooled Reactors
More acronyms/symbols:-D2O Deuterium oxide (heavy water)
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 12
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CANDU (CANada Deuterium- Uranium reactor)
Coolant: D2O
Tout: Low
Fuel: NU - LEU (Why?) Moderator: D2O
Power level: Med. - High Power density: Med.
Courtesy of Wikipedia User:Inductiveload. Used with permission.
Feasibility: High Adapted from: Wikimedia Commons MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 13
http://commons.wikimedia.org/wiki/File:CANDU_Reactor_Schematic.svghttp:22.033/22.33
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CANDU Special Features, Peculiarities
Courtesy of NSERC-UNENE Industrial Research Chair Program atUniversity of Waterloo. Used with permission.
Continuous fuel cycleExpensive moderator -~25% of capital cost
Moderator is unpressurized, thermally insulated
CANDU fuel bundle. Image source: http://www.civil.uwaterloo.ca/watrisk/research.html
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 14
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RBMK Reaktor Bolshoy Moshchnosti Kanalniy
Coolant: H2O
Tout: Low
Fuel: NU - LEU Moderator: Graphite Power level: High
Wikipedia Users: Fireice and Sakurambo. License CC BY-SA. Thiscontent is excluded from our Creative Commons license. For moreinformation, see http://ocw.mit.edu/fairuse.
Power density: Low Image source: Wikimedia Commons Feasibility: Med. (safety)
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 15
http://commons.wikimedia.org/wiki/File:RBMK_reactor_schematic.svghttp://ocw.mit.edu/fairusehttp:22.033/22.33
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RBMK Special Features, Peculiarities
Online refueling possible High positive void
coefficient Why? Improvements in design -No more graphite-tipped
control rods -More control rods
Photo courtesy of Wikipedia User:Cs szabo. License CC BY.
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 16
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SCWR Supercritial Water Reactor
Courtesy of Idaho National Laboratory. Used with permission.
Coolant: SC-H2O
Tout: Med.
Fuel: NU - LEU Moderator: SC-H2O
Power level: High Power density: High Feasibility: Low (now)
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 17
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SCWR Special Features, Peculiarities
Geothermania. All rights reserved. This content is excluded from our CreativeCommons license. For more information, see http://ocw.mit.edu/fairuse.
Phase diagram for water. Image source: http://geothermania.blogspot.com/2011/05/research-of-
supercritical-water-may.html
Very simple design Significant materials
concerns Coolant/moderator
voiding a non-issue High efficiency Start-up procedures (pre-
heating) to bring coolant supercritial
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 18
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Liquid Metal Cooled Reactors
More acronyms/symbols: -LBE Lead-bismuth eutectic -NaK Sodium-potassium alloy
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 19
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SFR (or NaK-FR) Sodium Fast Reactor
Courtesy of Idaho National Laboratory. Used with permission.
Coolant: Liquid sodium Tout: Med.
Fuel: NEU - HEU Moderator: None Power levels: All Power density: High Feasibility: Low-Med.
(now)
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 20
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SFR Special Features, Peculiarities
Courtesy of and copyright Bruno Comby / EFN - Environmentalists ForNuclear Energy - http://www.ecolo.org. Used with permission.
No pressurization Very high k, cP High material
compatibility High boiling margin Neutron activation
worker dose concerns Molten sodium at MONJU, Japan. Image source:
http://www.ecolo.org/photos/visite/monju_02/monju.sodium Na + H2O = RUN AWAY .hot.melted.jpg MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 21
http://www.ecolo.org/photos/visite/monju_02/monju.sodium.hot.melted.jpghttp://www.ecolo.org/photos/visite/monju_02/monju.sodium.hot.melted.jpghttp://www.ecolo.orghttp:22.033/22.33
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LFR (or LBEFR) Lead Fast Reactor
Courtesy of Idaho National Laboratory. Used with permission.
Coolant: Lead (or LBE) Tout: Med. (higher soon...)
Fuel: MEU Moderator: None Power levels: All Power density: High Feasibility: Low-Med.
(now)
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 22
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LFR Special Features, Peculiarities
High heat capacity Self-shielding Must melt coolant first Essentially no coolant
voiding possible Polonium creation Material corrosion
Alfa-class Russian submarine, using a LFR as its propulsion system. Image source: Wikimedia Commons Coolant cost (LBE)
(Public domain)
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 23
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Molten Salt Cooled Reactors
More acronyms/symbols:-FLiBe Lithium & beryllium fluoride salts
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 24
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MSR Molten Salt Reactor
Coolant: FLiBe, UF4 Tout: Med. - High
Fuel: MEU Moderator: Graphite Power levels: All Power density: High Feasibility: Med. (now)
Courtesy of Idaho National Laboratory. Used with permission.
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 25
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MSR Special Features, Peculiarities
Molten FLiBe. Image source: Wikimedia Commons
Unpressurized core ThF4/UF4 fluid can be
both fuel & coolant Very negative
temperature coeff. High neutron flux causes
Li3H, 3H+F-HF (hydrofluoric acid)
On-site salt reprocessing MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 26
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Core Group - Questions
Which coolant to use?What outlet temperature?How big of a reactor?Primary / secondary / tertiary cycles?Recuperator?How much electricity vs. process heat?Where in the cycle should process heat exit?
MIT Dept. of Nuclear Science and Engineering Dr. Michael P. Short, 2011 22.033/22.33 Nuclear Design Course Page 27
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