Nuclear Engineering

Fundamentals of Nuclear Physics and Radioactive Decay

Atomic Structure and Binding Energy

• Study the composition of the nucleus, including the roles of protons and neutrons in determining atomic stability and isotope formation.
• Analyze nuclear binding energy and the mass defect to understand why energy is released during nuclear reactions.
• Calculate the stability of different nuclides using the liquid drop model and the shell model of the nucleus.

Radioactive Decay Processes

• Examine the mechanics of alpha, beta, and gamma decay, including the conservation laws that govern these transitions.
• Master the mathematics of radioactive decay law, including half-life, mean life, and decay constants for single isotopes and complex decay chains.
• Identify the properties of different types of radiation and how they interact with matter through ionization and excitation.

Neutron Interaction and Transport Theory

Neutron Cross-Sections and Reaction Rates

• Understand microscopic and macroscopic cross-sections as measurements of the probability that a neutron will interact with a nucleus.
• Analyze different types of interactions, such as elastic scattering, inelastic scattering, radiative capture, and fission.
• Explore resonance absorption and how the energy of a neutron affects its likelihood of being captured by various materials.

Neutron Diffusion and Transport Equations

• Apply the Boltzmann transport equation to model the distribution of neutrons in space, energy, and time within a reactor.
• Utilize diffusion theory approximations to simplify the transport equation for practical engineering calculations in large reactor cores.
• Establish boundary conditions for neutron flux at interfaces between different materials, such as the core and the reflector.

Nuclear Reactor Theory and Core Design

The Fission Chain Reaction

• Analyze the fission process in heavy nuclei like Uranium-235 and Plutonium-239, focusing on the release of energy and additional neutrons.
• Master the six-factor formula used to determine the multiplication factor (k) and achieve a self-sustaining chain reaction.
• Differentiate between subcritical, critical, and supercritical states in a nuclear system.

Reactor Kinetics and Dynamics

• Study the critical role of delayed neutrons in controlling the rate of power changes within a reactor.
• Understand the point kinetics equations and how they describe the time-dependent behavior of the neutron population.
• Evaluate reactivity feedback mechanisms, such as the Doppler effect in fuel and the void coefficient in moderators, which ensure inherent reactor stability.

Thermal-Hydraulics in Nuclear Systems

Heat Generation and Conduction

• Calculate the volumetric heat generation rate within nuclear fuel pellets based on local neutron flux levels.
• Model the temperature distribution across the fuel, gap, and cladding to ensure structural integrity is maintained.
• Analyze the thermal conductivity of various fuel types and how it changes over the life of the reactor.

Coolant Flow and Heat Transfer

• Apply principles of fluid mechanics to calculate pressure drops and flow rates for different reactor coolants, including light water, heavy water, and liquid metals.
• Study convective heat transfer coefficients and the correlations used to determine the efficiency of heat removal from the fuel rods.
• Understand the Boiling Curve and the importance of avoiding the Critical Heat Flux (CHF) to prevent cladding failure.

Nuclear Materials and Radiation Effects

Structural Materials in High-Radiation Fields

• Investigate how intense neutron bombardment causes radiation damage, such as swelling, creep, and embrittlement in stainless steels and zirconium alloys.
• Calculate the displacement per atom (dpa) to quantify the cumulative damage to the crystal lattice of reactor components.
• Analyze the chemical interactions between the coolant and structural materials, focusing on corrosion and stress corrosion cracking.

Nuclear Fuel Engineering

• Examine the physical and chemical properties of uranium dioxide (UO2) and mixed oxide (MOX) fuels.
• Study the behavior of fission products, including the release of fission gases like Xenon and Krypton into the fuel-cladding gap.
• Understand pellet-cladding interaction (PCI) and the design requirements for fuel rods to withstand high pressure and temperature.

The Nuclear Fuel Cycle and Waste Management

Front-End Processes

• Explore the stages of the fuel cycle, including uranium mining, milling, and conversion to uranium hexafluoride.
• Master the techniques used for uranium enrichment, such as gas centrifuges and gaseous diffusion, to increase the concentration of fissile isotopes.
• Detail the fuel fabrication process, where enriched uranium is processed into ceramic pellets and loaded into fuel assemblies.

Back-End Processes and Waste Disposal

• Analyze the management of spent nuclear fuel, including short-term storage in cooling pools and long-term storage in dry casks.
• Study nuclear reprocessing technologies, such as the PUREX process, used to separate plutonium and unused uranium from fission products.
• Evaluate strategies for the permanent disposal of high-level radioactive waste in deep geological repositories.

Nuclear Reactor Safety and Protection Systems

Defense-in-Depth and Safety Design

• Understand the philosophy of defense-in-depth, utilizing multiple physical barriers to prevent the release of radioactive materials.
• Analyze the design and function of redundant safety systems, including Emergency Core Cooling Systems (ECCS) and containment structures.
• Distinguish between active safety systems that require power and passive safety systems that rely on natural forces like gravity and convection.

Probabilistic Risk Assessment (PRA)

• Utilize fault trees and event trees to identify potential accident sequences and calculate their probability of occurrence.
• Analyze Design Basis Accidents (DBA), such as the Loss-of-Coolant Accident (LOCA), to ensure reactor designs can withstand extreme conditions.
• Study the lessons learned from historical reactor incidents to improve modern safety protocols and regulatory standards.

Radiation Protection and Shielding Design

Biological Effects of Ionizing Radiation

• Differentiate between deterministic effects, such as radiation burns, and stochastic effects, such as the increased risk of cancer.
• Master the units of radiation measurement, including absorbed dose (Gray), equivalent dose (Sievert), and activity (Becquerel).
• Apply the ALARA principle (As Low As Reasonably Achievable) to minimize radiation exposure for workers and the public.

Radiation Shielding Principles

• Calculate the attenuation of gamma rays using the exponential attenuation law and buildup factors for different materials.
• Design effective shielding for neutron radiation using materials that slow down and then absorb neutrons, such as water, concrete, and boron.
• Determine the required thickness of shielding walls for various nuclear facilities to meet strict safety regulations.