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Questions and Answers
Which coolant is associated with the Gas Fast Reactor (GFR)?
Which coolant is associated with the Gas Fast Reactor (GFR)?
What is the outlet temperature range of the Lead Fast Reactor (LFR)?
What is the outlet temperature range of the Lead Fast Reactor (LFR)?
Which type of processing is utilized by the Molten Salt Reactor (MSR)?
Which type of processing is utilized by the Molten Salt Reactor (MSR)?
What is the primary fuel type used in the Supercritical Water Reactor (SCWR)?
What is the primary fuel type used in the Supercritical Water Reactor (SCWR)?
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Which reactor type operates at the highest outlet temperature mentioned?
Which reactor type operates at the highest outlet temperature mentioned?
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What feature is emphasized in the design of Evolutionary PWRs and BWRs to address safety concerns?
What feature is emphasized in the design of Evolutionary PWRs and BWRs to address safety concerns?
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Which of the following reactors has a larger pressurizer compared to traditional designs?
Which of the following reactors has a larger pressurizer compared to traditional designs?
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Which reactor is designed with a centrifugal pump internal to the reactor vessel to minimize the risk of Loss of Coolant Accident (LOCA)?
Which reactor is designed with a centrifugal pump internal to the reactor vessel to minimize the risk of Loss of Coolant Accident (LOCA)?
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What is a notable characteristic of the System 80+ PWR by ABB/CE?
What is a notable characteristic of the System 80+ PWR by ABB/CE?
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What type of cooling system is utilized in the Advanced Passive 600Mwe PWR to manage decay heat?
What type of cooling system is utilized in the Advanced Passive 600Mwe PWR to manage decay heat?
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What is the primary fuel used in breeder reactors like the LWBR?
What is the primary fuel used in breeder reactors like the LWBR?
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What is one of the drawbacks of using the LWBR system?
What is one of the drawbacks of using the LWBR system?
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Which Generation IV reactor is aimed at supporting a Nuclear Hydrogen Program?
Which Generation IV reactor is aimed at supporting a Nuclear Hydrogen Program?
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What is the overall efficiency of the reactor design stated in the content at 24 MPa and 540°C?
What is the overall efficiency of the reactor design stated in the content at 24 MPa and 540°C?
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Which of the following is NOT one of the Generation IV systems selected for further development?
Which of the following is NOT one of the Generation IV systems selected for further development?
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What aspect is emphasized for maintaining efficiency in breeder reactors?
What aspect is emphasized for maintaining efficiency in breeder reactors?
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What is a key element for the technical feasibility of breeder reactors noted in the content?
What is a key element for the technical feasibility of breeder reactors noted in the content?
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Which Generation IV system is noted for potentially reducing spent fuel?
Which Generation IV system is noted for potentially reducing spent fuel?
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What is a characteristic feature of the Simplified Boiling Water Reactor (SBWR)?
What is a characteristic feature of the Simplified Boiling Water Reactor (SBWR)?
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Which of the following is NOT a type of breeder reactor?
Which of the following is NOT a type of breeder reactor?
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What is a primary disadvantage of using liquid metal coolants in Liquid Metal Fast Breeder Reactors (LMFBR)?
What is a primary disadvantage of using liquid metal coolants in Liquid Metal Fast Breeder Reactors (LMFBR)?
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What type of fuel is typically used in the Gas Cooled Fast Breeder Reactor (GCFR)?
What type of fuel is typically used in the Gas Cooled Fast Breeder Reactor (GCFR)?
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Which property of the Molten Salt Breeder Reactor (MSBR) makes it an effective thermal breeder?
Which property of the Molten Salt Breeder Reactor (MSBR) makes it an effective thermal breeder?
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What is the typical operation temperature range for the Liquid Metal Fast Breeder Reactor (LMFBR)?
What is the typical operation temperature range for the Liquid Metal Fast Breeder Reactor (LMFBR)?
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Which type of breeder reactor is known for not using a radioactive coolant?
Which type of breeder reactor is known for not using a radioactive coolant?
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Which of the following statements about the advantages of LMFBR is correct?
Which of the following statements about the advantages of LMFBR is correct?
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Study Notes
NUCE 402: Introduction to Nuclear System and Operation
- Course name: NUCE 402: Introduction to Nuclear System and Operation
- Course instructor: Dr. Ahmed Alkaabi
- Chapter 1-3 topic: Advanced PWR and BWR, Gen-IV reactors
Evolutionary PWR & BWR
- Background: Increased construction costs, increased safety requirements
- Passive safety system: Systems using gravity and temperature
- System Simplification + Constructability: Systems 80+ by CE, EPR1600, APR1400
- Advanced Boiling Water Reactor (ABWR) by GE
- Advanced Passive Cooling System: Advanced Passive 600 (AP600) & AP1000 by Westinghouse, ESBWR (Economic Simplified Boiling Water Reactor) by GE
The Evolutionary and Advanced Light water Reactor
- System 80+ PWR by ABB/CE: Large spherical double wall, concrete and steel containment, larger water inventory, 33% bigger pressurizer, 25% bigger secondary side
Advanced Boiling Water Reactor(ABWR) by GE
- Centrifugal pump internal to RXV: Minimizing the risk of LOCA
Advanced Passive 600Mwe PWR by Westinghouse
- Passive containment cooling: Ultimate heat sink for decay heat, 30% larger pressurizer in the event of a LOCA
Simplified Boiling Water Reactor(SBWR) by GE
- Gravity-driven cooling system (GDCS): Natural circulation of the reactor coolant
- No pumps in RXV: Passive containment cooling system (PCCS), Automatic depressurization system (ADS)
Breeder Reactors
- Fuel: 235U → 238U
- Types of breeder reactors: LMFBR, GCFR, MSBR, LWBR
- Fertile material: 238U/232Th
- Fissile material: 239Pu/233U
Liquid Metal Fast Breeder Reactor (LMFBR)
- Liquid metal: Na, K
- Advantages: No elastic scattering, good heat transfer, high boiling poin, no corrosion
- Disadvantages: Melting point, highly chemically reactive, neutron absorption
Experience - Significant commercialization stage
- Super Phenix (Fr.): Pool-type, Monju (Japan) (280MWe): Loop-type
- Fuel: High enriched fuel: 15~35%, Stainless steel cladding
- Steam:
500C, 1618MPa, Efficiency ~ 40%
Breeder Reactors - GCFR
- From HTGR: Fuel: a mixture of PuO2 and UO2
- Core: Similar to core of an LMFBR
- Helium pressure: 10.5 MPa
- Inlet: 298°C and Outlet: 520°C
- Coolant: No radioactive
Breeder Reactors - MSBR
- Thermal breeder: 233U-Thorium cycle
- 233U: Only fissile isotope capable of breeding in thermal reactor.
- Mixture of fertile material and coolant (various fluoride salts)
- Melt: to clear, non-viscous fluid
- Very small thermal neutron: absorption cross section
- Good heat transfer, low vapor pressure: at high temperature
- No damage by radiation, chemically stable: 233 Pa must be removed
- Good neutron economy: Overall efficiency:~44% at 24MPa and 540°C
- Drawback: maintenance and repair
Breeder Reactors - LWBR
- Fuel: 233U
- By reducing: the amount of water relative to fuel in the core
- Shifting the energy: spectrum of the neutrons
- Strict control: of losses of neutrons
- Enough excess 233U: to compensate for the loss of 233U
- Technical feasibility: was confirmed at Shippingport, USA
Gen IV - Technology
- Introduces six Generation IV systems chosen by Generation IV International Forum for further development.
- Systems: Gas-cooled Fast Reactor (GFR), Lead-cooled Fast Reactor (LFR), Sodium-cooled Fast Reactor (SFR), Molten Salt Reactor (MSR), Supercritical Water-cooled Reactor (SCWR), Very High Temperature Reactor (VHTR)
- Surveys system-specific R&D needs for all six systems
- Collects crosscutting R&D needs
- Design and evaluation methods, materials, energy conversion
Gen IV - Demonstration
- Gen IV Top Priority: VHTR + H2, NGNP (US), NHDD (Kor.)
- Next-Generation Nuclear Plant: Collaborative with international community, industry, Demonstrate H2 and direct-cycle electricity production, Result in a commercially viable plant design
- Gen IV Second Priority: GFR, LFR, SFR, MSR, SCWR, Fast Reactor and Advanced Fuel Cycle Initiative
SFR: Gen IV Technology Roadmap
- Candidate Reactor: for Global Nuclear Energy Partnership (GNEP)
- Reduce spent fuel: Burn trans-U with long half-lives
- Reactor Parameters: Outlet Temperature (530-550 °C), Pressure (~1 Atmospheres), Rating (1000-5000 MWth), Fuel (Oxide or metal alloy), Cladding (Ferritic or ODS ferritic), Average Burnup (~150-200 GWD/MTΗΜ), Conversion Ratio (0.5-1.30), Average Power Density (350 MWth/m³)
VHTR: Gen IV Technology Roadmap
- Candidate Reactor: for Nuclear Hydrogen Program
- Very high temp.: needed for H-production
- Co-generation & process heat: utilization options
- Reactor Parameters: Reactor power (600 MWth), Coolant inlet/outlet temperature (640/1000°C), Core inlet/outlet pressure (dependent on process), Helium mass flow rate (320 kg/s), Average power density (6-10 MWth/m³), Reference fuel compound (ZrC-coated particles in blocks, pins or pebbles), Net plant efficiency (>50%)
Gen IV Technology Roadmap
- Data on various reactor systems: GFR, LFR, MSR, SFR, SCWR, VHTR
- Recycle Process, Outlet Temp., Neutron Spectrum, Coolant, Fuel
Small Modular Reactor (SMR)
- Advanced SMRs (modular and integrated-PWRs)
- Data on various SMRs: CAREM-25, SMART, VBER-300, WWER-300, ABV-6, HTR-PM, mPower, NuScale, Westinghouse SMR, CEFR, 4S, PFBR-500
Homework #1
- Due date: One week before class
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Description
Test your knowledge on various types of nuclear reactors, including the Gas Fast Reactor and the Supercritical Water Reactor. This quiz covers key characteristics, designs, and safety features of modern reactor systems. Challenge yourself to identify fuels, cooling systems, and innovative designs in advanced nuclear technology.
