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 EM 2 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 UO 2 Standard LWR fuel in Metallic U-Pu or U-Pu-Zr Alloy 17x17 assembly, Westinghouse Fuel Design Used Nuclear Fuel or depleted uranium UO 2 17x17 grid SiC or ZrC coating on UCO or UO 2 in 27 rod prism U-Pu-Zr Uranium Nitride (UN) in HT-9 (high temp ceramic) tubes Standard 17x17 PWR LWR Fuel LWR Fuel UO 2 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 ^4298+^4299^4299↓ → 142 ^4399+−+^2759+^2760Decay ^4299↓ → 142 ^4399+−+^4399↓ → 141 ^4399↓ →↑249 ┴^4499^4399↓ → 141 ^4399↓ →↑249 ┴^4499Galena, 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.

Transcript of May 7, 2013 Terp Atomics: Exploring Small Modular … Atomics Babock and ... per kW) 6-9¢/kWh,...

Page 1: May 7, 2013 Terp Atomics: Exploring Small Modular … Atomics Babock and ... per kW) 6-9¢/kWh, $4000/kW ... Molybdenum-99 and cobalt-60 are important medical isotopes that

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.