may 7, 2013 terp atomics: exploring small modular … atomics babock and ... per kw) 6-9¢/kwh,...
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Name NuScale 4S Westinghouse SMR EM2 mPower Antares PRISM G4M HI-SMUR
140 AP1000 ESBWR
Designer NuScale Power Toshiba Westinghouse General
Atomics Babock and
Wilcox Areva GE Hitachi Gen4 Energy Holtec International Westinghouse GE Hitachi
Type LWR LMFBR PWR Helium Cooled LWR Helium Cooled LMFB (Sodium) LMFBR (LBU) PWR PWR BWR Rating (MWth, MWe, Eff%) 160, 45, 38% 30, 10, 33% 800, 225, 28% 500, 240, 48% 500,180, 31% 600 MWth 840, 311, 37% 70, 25, 36% 469, 145, 31% 3400, 1200,
35% 4550, 1550,
34% Cost (¢ per kWh,
per kW) 6-9¢/kWh, $4000/kW
5-7¢/kWh, $2500/kW $4500/kW 6¢/kWh $5000/kW 4 Billion $2572/kW $5000/kW $5000/kW $2302/kW $3500/kW
Coolant Light Water Sodium Light Water Helium Light Water Helium Sodium Pb-Bi Eutectic Light Water Light Water Light Water Moderator Light Water None Light Water None Light Water None None None None Light Water Light Water
Safety Systems
Air/Water Passive, Internal
Pressure Vessel
Components
Air Passive, Forced Cooling
Passive Safety, Internal Pressure
Vessel Components
SiC cladding, Helium
Passive, Air Heat
Exchanger
Water Passive, Internal
Pressure Vessel
Components
Water Passive Air Passive Stainless steel cladding,
boron carbide control rods,
Water Passive Water Passive Water Passive
Deployment Train, Truck, Barge Barge Barge Train, Truck Train Train Train <20 metric tons, Truck Train, Truck Difficult Difficult
Fuel/Type UO2
Standard LWR fuel in
Metallic U-Pu or U-Pu-Zr
Alloy
17x17 assembly, Westinghouse Fuel
Design
Used Nuclear Fuel or
depleted uranium
UO2 17x17 grid
SiC or ZrC coating on
UCO or UO2 in 27 rod prism
U-Pu-Zr Uranium Nitride (UN) in
HT-9 (high temp ceramic) tubes
Standard 17x17 PWR LWR Fuel LWR Fuel
UO2
Fuel Enrichment 4.95% 17% and 19% <5% 12% 5% 26% Pu, 10% Zr 19.75% <5 wt% Enrichment 4.8% 4.2%
Refueling Frequency 24 months 30 years 24 months 30 years 4 years 18 months, 1/3
replaced 10 years 3+ years 18 months
20% 12 month cycle,
42% 24 month cycle
Mechanical Engineering Design Day May 7, 2013
ENME472 - Integrated Product and Process Design and Development
What are SMR’s? Comparison of Reactors
Mike Gustafson, Perry Mahle, Keaton Pavier, Spencer Robinson, William Wieprecht
Terp Atomics: Exploring Small Modular Reactors
Medical Isotope Production
Oil Sands Extraction
Alaska China Comparison with Current Fleet
The latent heat from a SMR can be used to extract oil from tar sands. Current methods for steam production use natural gas combustion. • Steam Assisted Gravity Drainage (SAGD)
o Parallel, Horizontal Wells o Steam injected into top well, oil and condensate removed from
lower well • Cyclic Steam Stimulation (CSS)
o Steam Injection, Soak, Oil Production, Repeat • Well Lifetime: 6 – 8 years • Steam temperature: 300ºC
Small Modular Reactors, also known as SMRs, are small-scale nuclear power plants, with a range of roughly 10-300 MWe production. Current SMRs being designed and produced incorporate all of the most modern technologies and over 60 years of industry experience in building nuclear reactors. It appears that in recent years, there is a new revival in the use of nuclear power using smaller reactors for increased manufacturability, scalability, and increased passive safety systems.
Demand • China is rapidly industrializing • Power consumption increasing greatly
each year. Nuclear Power • China is currently developing over 12 1000
MW nuclear power plants. SMR’s • SMR’s will be advantageous through their
modularity. To best accommodate China’s future power demands, SMR’s can be built to work in conjunction with planned large scale reactors.
Power Source Expected Price
for China ($/MWh)
Wind 96 Nuclear 110 Solar
(Photoelectric) 152
Solar (Thermal) 242 Coal 110
Small Modular Safe 10-300 MWe output compared to 1000MWe
output of current plants Transportable by truck or train
Designed to work in conjunction with each other
Standard design throughout all reactors
Passive cooling systems Greater walkaway time Lower proliferation risk
Molybdenum-99 Technium-99m Cobalt-60
Half Life (hr) 65.9736 6.0058 46204.8
Production ^42↑98↓𝑀𝑜 +𝑛→ ^42↑99↓𝑀𝑜 ^42↑99↓𝑀𝑜 →𝛽 142 𝑘𝑒𝑉┴ ^43↑99𝑚↓𝑇𝑐 + 𝛽↑− + 𝑣 ↓𝑒 ^27↑59↓𝐶𝑜 +𝑛→ ^27↑60↓𝐶𝑜
Decay ^42↑99↓𝑀𝑜 →𝛽 142 𝑘𝑒𝑉┴ ^43↑99𝑚↓𝑇𝑐 + 𝛽↑− + 𝑣 ↓𝑒
^43↑99𝑚↓𝑇𝑐 →𝛾 141 𝑘𝑒𝑉┴ ^43↑99↓𝑇𝑐 →𝛽↑− 249
𝑘𝑒𝑉┴^44↑99↓𝑅𝑢
^43↑99𝑚↓𝑇𝑐 →𝛾 141 𝑘𝑒𝑉┴ ^43↑99↓𝑇𝑐 →𝛽↑− 249
𝑘𝑒𝑉┴^44↑99↓𝑅𝑢
Galena, AK • Inland Alaska, requires approx. 1 Mwe • No roads out of city; No connection to external electric grid
Why Consider an SMR?
• Cost of Electricity o Currently ~70 cents/kWh o Natural Gas, requires long term storage for yearly supply o SMRs rated at 6-9 cents/kWh
• Power Source Reliability o Wind and Annual Solar availability poor o No Hydropower near Galena o Traditional Nuclear Plants are too large and installation is too long
Molybdenum-99 and cobalt-60 are important medical isotopes that can be created by bombarding natural isotopes with neutrons. Samples of the materials can be inserted in through-tubes of reactors, although having a through-tube results in a higher stress intensity factor and requires thicker walls. This is more of a problem with PWR versus other reactors since they run at much higher pressures.
Passive Cooling: Gen II Reactors relied on active pumps and systems to remove heat generated by nuclear decay. Gen IV+ remove decay heat through passive systems. Some have a walk away time of over 5 days.
Nuclear reactor designs are categorized by “generation”; that is, Generation I, II, III, III+, and IV. The present analysis of existing reactor concepts focuses on six key reactor attributes: Cost-Effectiveness, Safety, Security and Nonproliferation, Grid Appropriateness, and Commercialization Roadmap.