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Nuclear Material Science

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Uranium-235

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Usage: Fuel in thermal nuclear reactors; Properties: Fissile isotope, undergoes fission with thermal neutrons

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Control Rods

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Usage: Regulate the fission reaction rate; Properties: Made of neutron absorbing materials

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Thorium-232

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Usage: Fuel in thorium reactors, can breed U-233; Properties: Fertile material, higher melting point than uranium

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Neutron Cross-Section

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Usage: Determines the likelihood of neutron reactions; Properties: Varies with isotope and neutron energy

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Reactor Pressure Vessel (RPV)

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Usage: Contains the nuclear reactor core and coolant; Properties: Designed to withstand high pressures and radiation

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Cadmium

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Usage: Neutron absorber in control rods; Properties: High neutron absorption cross-section, used in safety systems

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Uranium-238

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Usage: Breeder reactors to create fissile material; Properties: Fertile material, captures neutrons to become Plutonium-239

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Neutron Fluence

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Usage: Impacts material degradation in reactors; Properties: Measure of neutron exposure over time, leads to embrittlement and swelling

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Tungsten

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Usage: Radiation shielding due to high density; Properties: High melting point, high density, radiation absorbent

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Fission Product Gases

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Usage: Must be managed in fuel design; Properties: Include noble gases like krypton and xenon, which can cause fuel rod swelling

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Zirconium Alloys

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Usage: Fuel cladding in nuclear reactors; Properties: Low neutron absorption cross-section, corrosion resistant

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Radioactive Decay Heat

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Usage: Must be considered in reactor shutdown and safety; Properties: Heat produced from decay of fission products, continues after reactions stop

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Heavy Water (D2O)

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Usage: Neutron moderator and coolant; Properties: Slows neutrons effectively, has a low neutron absorption cross-section

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Stainless Steel

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Usage: Structural material in reactors, fuel cladding; Properties: Corrosion resistance, good mechanical properties

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Plutonium-239

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Usage: Fuel in fast breeder reactors; Properties: Fissile material, can be bred from Uranium-238

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Beryllium

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Usage: Neutron reflector and moderator; Properties: Low neutron absorption cross-section, high thermal conductivity

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Thermal Conductivity of Fuel

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Usage: Impacts fuel temperature and performance; Properties: High thermal conductivity helps remove heat from fuel efficiently

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Neutron Moderators

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Usage: Slows down fast neutrons for efficient fission; Properties: Light atomic mass, low neutron absorption

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Graphite

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Usage: Neutron moderator; Properties: High melting point, good thermal conductivity, low neutron absorption

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Lead

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Usage: Radiation shielding; Properties: Effective gamma-ray shielding due to high atomic number and density

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Sodium

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Usage: Coolant in fast breeder reactors; Properties: High thermal conductivity, low neutron moderation

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Nuclear Fusion Materials

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Usage: In fusion reactors, as fuel and reactor components; Properties: High thermal resistance, withstand extreme environments

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Retention of Fission Products

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Usage: Safety property of nuclear fuel; Properties: Fuel matrix holds fission products to prevent release

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Carbon-14

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Usage: Byproduct of nuclear reactors; Properties: Long-lived radioactive isotope, biologically active

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Thermal Neutrons

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Usage: Used in thermal nuclear reactors to sustain fission; Properties: Low energy neutrons at thermal equilibrium with the environment

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Boron

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Usage: Neutron absorber for control systems and safety; Properties: High neutron cross-section, commonly used in control rods

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Nuclear Waste

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Usage: Must be safely stored and managed; Properties: Highly radioactive, long-lived isotopes

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MOX Fuel

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Usage: Alternative to uranium fuel in thermal reactors; Properties: Blend of plutonium oxide and uranium oxide

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Fast Neutron Spectrum

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Usage: Characteristic of fast breeder reactors; Properties: Higher neutron energies that improve breeding ratios

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Nuclear Poison

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Usage: Absorbs neutrons, impacting reactor control; Properties: High neutron capture cross-section, forms from certain fission products

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Hafnium

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Usage: Neutron absorber in control rods; Properties: Very high thermal neutron absorption cross-section

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Nuclear Fuel Pellets

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Usage: Contained in fuel rods to sustain nuclear reactions; Properties: Typically composed of UO2 or MOX, high energy density

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Ceramic Fuel

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Usage: Encapsulate fissile material; Properties: High melting point, thermal stability, and chemical inertness

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Reactivity Coefficient

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Usage: Describes the reactor's response to temperature changes; Properties: Negative coefficients improve safety by reducing reactivity as temperature rises

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