Transcript Sodium-Cooled Fast Reactor

Sodium-Cooled Fast Reactor
Thorium Based Metallic Closed
Fuel Cycle
Fynan, Mar, Sirajuddin
What is DCTRU?
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DCTRU = Dreams Come TRU, where TRU = Transuranics
Current Generation II Light Water Reactors (LWRs) utilize a thermal spectrum of neutrons to induce
fission in a 238U/235U based fuel
These reactors provide approximately 20% of the United States’ power generation
A typical LWR produces on the order of 25-30 tonnes of nuclear waste per year. 113 nuclear power
plants in the US ≈ 4000 tonnes per year. Currently, over 115,000 tonnes of nuclear waste is being
stored in repositories in the US. Transuranics make up the majority of waste produced via fission
reactions in LWRs
DCTRU lends a compassionate and understanding ear to:
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The environment
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Safety concerns
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Economic and ethical electricity production
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Future generations’ stewardship burden (e.g. Yucca Mountain [YM])
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Decomissioning of nuclear arms
Global Nuclear Energy Partnership (GNEP) and the Generation IV Technology Roadmap has
selected SFR as a candidate for further research and development as part
of the Advanced Fuel Cycle Initiative (AFCI)
Fynan, Mar, Sirajuddin
SFR Uses Today’s Nuclear Waste
as Tomorrow’s Fuel
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GNEP, AFCI, and DCTRU aim to provide for cleaner, safer, more recyclable energy for the world of
tomorrow.
SFR accomplishes these goals by utilizing a fast neutron spectrum to induce fissions in Transuranics
(TRUs), and minor actinides (MAs) produced as waste by present LWRs.
Furthermore, using 232Th as a host fuel, Generation IV reactors such as SFR will take advantage of
thorium’s high burnup to reduce future waste production while accounting for the energy needs of
future generations.
The SFR has an inherently modular design, for flexible application
The SFR is proliferation resistant
Passive safety features of the SFR include :
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Large boiling margin
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Lack of corrosive effects
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Low operating pressure (~ 1 atm)
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Overall simplicity of design
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Sodium pool design
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Subterranean core
The reactor produces economically competitive power
Fynan, Mar, Sirajuddin
Design
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Sodium-Cooled Fast Reactor with target power
output of 1000 MWt
Small, pancake core
(Thorium-Uranium-Plutonium)Zr fuel
with tandem use of a targeted actinide mechanism
Fuel pin assembly
Sodium coolant pool
Austenitic stainless steel used for structural and
piping materials
Intermediate heat exchangers (IHX)
Fast neutron spectrum for reduction of Plutonium and
minor actinides (MAs)
Fynan, Mar, Sirajuddin
Modes of Analysis and Modeling
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MC2 for lattice physics calculations
Rebus3 for multi-group diffusion analysis
Fynan, Mar, Sirajuddin