Nuclear Reactor Types and Features Quiz

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Questions and Answers

Which coolant is associated with the Gas Fast Reactor (GFR)?

  • Lead
  • Water
  • Gas (correct)
  • Sodium

What is the outlet temperature range of the Lead Fast Reactor (LFR)?

  • 900°C to 950°C
  • 850°C to 900°C
  • 1000°C
  • 550°C to 800°C (correct)

Which type of processing is utilized by the Molten Salt Reactor (MSR)?

  • Aqueous
  • Gas
  • Pyro
  • Once-through (correct)

What is the primary fuel type used in the Supercritical Water Reactor (SCWR)?

<p>Uranium Dioxide (UO2) (A)</p> Signup and view all the answers

Which reactor type operates at the highest outlet temperature mentioned?

<p>Very High Temperature Reactor (VHTR) (D)</p> Signup and view all the answers

What feature is emphasized in the design of Evolutionary PWRs and BWRs to address safety concerns?

<p>Passive safety systems (D)</p> Signup and view all the answers

Which of the following reactors has a larger pressurizer compared to traditional designs?

<p>Advanced Passive 600Mwe PWR (D)</p> Signup and view all the answers

Which reactor is designed with a centrifugal pump internal to the reactor vessel to minimize the risk of Loss of Coolant Accident (LOCA)?

<p>Advanced Boiling Water Reactor (ABWR) (D)</p> Signup and view all the answers

What is a notable characteristic of the System 80+ PWR by ABB/CE?

<p>Larger containment vessel size (A)</p> Signup and view all the answers

What type of cooling system is utilized in the Advanced Passive 600Mwe PWR to manage decay heat?

<p>Passive containment cooling system (B)</p> Signup and view all the answers

What is the primary fuel used in breeder reactors like the LWBR?

<p>233U (D)</p> Signup and view all the answers

What is one of the drawbacks of using the LWBR system?

<p>Maintenance and repair (D)</p> Signup and view all the answers

Which Generation IV reactor is aimed at supporting a Nuclear Hydrogen Program?

<p>Very High Temperature Reactor (D)</p> Signup and view all the answers

What is the overall efficiency of the reactor design stated in the content at 24 MPa and 540°C?

<p>44% (D)</p> Signup and view all the answers

Which of the following is NOT one of the Generation IV systems selected for further development?

<p>Heavy Water Reactor (A)</p> Signup and view all the answers

What aspect is emphasized for maintaining efficiency in breeder reactors?

<p>Reducing water relative to fuel (B)</p> Signup and view all the answers

What is a key element for the technical feasibility of breeder reactors noted in the content?

<p>Strict control of neutron losses (A)</p> Signup and view all the answers

Which Generation IV system is noted for potentially reducing spent fuel?

<p>Sodium Fast Reactor (C)</p> Signup and view all the answers

What is a characteristic feature of the Simplified Boiling Water Reactor (SBWR)?

<p>Uses a gravity-driven cooling system (C)</p> Signup and view all the answers

Which of the following is NOT a type of breeder reactor?

<p>High Temperature Gas Reactor (HTGR) (C)</p> Signup and view all the answers

What is a primary disadvantage of using liquid metal coolants in Liquid Metal Fast Breeder Reactors (LMFBR)?

<p>Highly chemically reactive (B)</p> Signup and view all the answers

What type of fuel is typically used in the Gas Cooled Fast Breeder Reactor (GCFR)?

<p>Uranium dioxide and Plutonium dioxide (A)</p> Signup and view all the answers

Which property of the Molten Salt Breeder Reactor (MSBR) makes it an effective thermal breeder?

<p>Very small thermal neutron absorption cross section (B)</p> Signup and view all the answers

What is the typical operation temperature range for the Liquid Metal Fast Breeder Reactor (LMFBR)?

<p>Near 882°C at 1 atm (D)</p> Signup and view all the answers

Which type of breeder reactor is known for not using a radioactive coolant?

<p>Gas Cooled Fast Breeder Reactor (GCFR) (B)</p> Signup and view all the answers

Which of the following statements about the advantages of LMFBR is correct?

<p>High boiling point allowing for lower operational pressure (C)</p> Signup and view all the answers

Flashcards

Evolutionary PWRs

A newer generation of Pressurized Water Reactors (PWRs) that addressed issues like high construction costs and safety concerns. They incorporate features like passive safety systems, simpler designs, and increased water inventory for better safety.

Advanced BWRs (ABWR)

Boiling Water Reactors (BWRs) that have been enhanced with features like an internal centrifugal pump for the reactor coolant, resulting in reduced risk of a loss-of-coolant accident (LOCA).

Passive Containment Cooling (AP600)

A passive safety system in AP600 PWRs, which acts as a final heat sink to cool down the reactor in case of a LOCA. It utilises gravity and natural convection for heat removal.

Larger Pressurizer (AP600)

A key design feature in AP600 PWRs, with a significantly larger size compared to older designs. It provides a larger volume for pressure relief and ensures proper operation of the passive safety systems.

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Double-Wall Containment (System 80+)

A notable design feature of System 80+ PWRs, consisting of two layers (concrete and steel) for enhanced safety and containment of the reactor. This design allows for steam expansion and provides a heat sink in case of an accident.

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Breeder Reactors - LWBR

A type of reactor that uses 233U as fuel. It aims to reduce the amount of water relative to fuel, adjust the energy spectrum of neutrons, and control neutron losses to achieve a good neutron economy.

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Gen IV Reactors

A generation of reactor designs intended to improve on existing technologies, focusing on safety, efficiency, and waste management.

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Lead-cooled Fast Reactor (LFR)

A Gen IV reactor type characterized by using lead as a coolant. Offers advantages in safety and efficiency.

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Molten Salt Reactor (MSR)

A Gen IV reactor type that uses molten salt as coolant and fuel. Holds potential for high efficiency and inherent safety.

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Sodium-cooled Fast Reactor (SFR)

A Gen IV reactor type utilizing sodium as a coolant. Advantages include excellent heat transfer properties and high thermal efficiency.

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Very High Temperature Reactor (VHTR)

A Gen IV reactor designed to produce hydrogen as a fuel and to generate electricity. It operates at very high temperatures.

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SFR: Gen IV Technology Roadmap

A reactor type under development that aims to burn transuranic elements, reducing long-lived radioactive waste.

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VHTR: Gen IV Technology Roadmap

This reactor is a candidate for the Nuclear Hydrogen Program. It operates at very high temperatures.

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Simplified Boiling Water Reactor (SBWR)

A type of nuclear reactor that uses a gravity-driven cooling system (GDCS) for safety. This means the reactor relies on natural circulation of the coolant instead of pumps to remove heat in case of an emergency. No pumps in the reactor coolant system.

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Passive Containment Cooling System (PCCS) in SBWRs

A passive safety system in SBWRs that uses natural convection to cool down the reactor containment in case of an accident. It relies on gravity and large water pools to remove heat without relying on external power.

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Automatic Depressurization System (ADS) in SBWRs

A system used in SBWRs that automatically vents steam from the reactor pressure vessel if pressure rises too high, reducing pressure and preventing a meltdown.

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Breeder Reactor

A nuclear reactor that can produce more fissionable material (like plutonium) than it consumes. It relies on a high-energy neutron flux to achieve This process is called "breeding".

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Liquid Metal Fast Breeder Reactor (LMFBR)

A type of breeder reactor that uses liquid sodium or potassium as the coolant. Advantages include good heat transfer and high boiling point. Disadvantages include the need for specific materials and safety risks associated with sodium's properties.

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Gas Cooled Fast Breeder Reactor (GCFR)

A breeder reactor that uses helium as the coolant. It is based on the HTGR and features a high-temperature core and a closed-loop helium cycle. The main advantage is the non-radioactive nature of helium.

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Molten Salt Breeder Reactor (MSBR)

A breeder reactor that uses a molten salt mixture as the coolant and fuel carrier. It operates at high temperatures and offers potential advantages in terms of safety and efficiency. This type uses the Thorium cycle for breeding.

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Light Water Breeder Reactor (LWBR)

A breeder reactor that uses light water as coolant (similar to PWRs) but is designed with special fuel composition to produce more plutonium than it consumes. It offers advantages in terms of fuel economy but poses challenges in its operation.

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Fast Reactor

A type of nuclear reactor that uses a fast neutron spectrum, allowing for efficient utilization of uranium and plutonium. It typically uses a liquid metal coolant like sodium.

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Thermal Reactor

A type of reactor that uses a slower neutron spectrum, requiring more fuel but offering higher safety margins. It often utilizes water as a coolant.

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Co-generation Reactor

A type of nuclear reactor where the heat produced is not only used to generate electricity but also for other applications like industrial processes or heating.

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Small Modular Reactor

A nuclear reactor design that focuses on small size and modularity, making it easier to transport and install in locations with limited space.

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Generation IV Reactor

A generation of nuclear reactors with advanced features like passive safety systems and improved fuel efficiency, aiming for enhanced safety and sustainability.

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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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NUCE 402: Introduction to Nuclear System and Operation Lecture Notes PDF

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