Study Notes on Diffusion and Irradiation Induced Defects in Nuclear Engineering
NC STATE UNIVERSITY - Department of Nuclear Engineering
Diffusion - Continued
Steady-State Diffusion
Definition: ‘Steady-state’ refers to a situation in which the rate of diffusion is independent of time.
Fick’s 1st Law: Used to describe steady-state diffusion, expressed as:
Simplification of Concentration Gradient: For a linear concentration gradient:
Units:
- Flux, J: [mol/cm²s] or [kg/m²s]
- Diffusion coefficient, D: [m²/s]
- Concentration, C: [g/cm³]
- Position, x: [cm]
Example Calculation (Steady-State Diffusion)
- Given:
- Concentration gradient:
- Flux (J) calculation:
- Concentration gradient:
- Physical Set-Up: Inner surface exposed to coolant (Material 1) and outer surface with fuel (Material 2).
Non-Steady State Diffusion
Definition: In non-steady state diffusion, the concentration of diffusing species is a function of both time and position. Denoted as:
Fick’s Second Law: Used for non-steady state, expressed as:
Example of Copper Diffusing into Aluminum
- Conditions:
- At time t = 0: Initial concentration, $C_0$ for $0 \leq x \leq \infty$.
- At time t > 0: Surface concentration, $C_S$ at $x = 0$ (constant surface concentration).
- At infinity ($x = \infty$): Concentration remains $C_0$.
- Situation: Copper atoms diffuse into the aluminum bar, starting from a pre-existing concentration.
Solution and Error Function for Non-Steady State Diffusion
General solution:
Where $z$ is defined based on diffusion parameters:
Error Function (erf): Values are tabulated in Table 5.1 in the reference text.
Application Example: Lithium Diffusion into Cladding
- Context: In molten salt reactors (MSRs), lithium diffuses into structural alloys.
- Assumptions:
- Treat solid as semi-infinite with constant surface concentration.
- Initially, no lithium is present inside the material.
- Given Data:
- Surface concentration: $C_S = 0.10 ext{ wt% Li}$.
- Initial concentration: $C_0 = 0$.
- Diffusion coefficient: $D = 5.0 \times 10^{-9} m²/s$.
- Time of exposure: $t = 100$ hours = $3.6 \times 10^{5}s$.
- Depth: $x = 0.2 mm = 2 \times 10^{-4} m$.
- Objective: Find concentration at depth $x$ using the diffusion equation and previously defined error function.
Irradiation Induced Defects
Definition of Irradiation Damage
- Irradiation Damage: Defined as structural and chemical changes due to high-energy radiation.
- Key Effects from Irradiation:
- Atomic Displacements: Generate radiation-induced defects such as dislocations, dislocation loops, vacancies, and interstitials.
- Phase Stability Changes: Alterations in the phase stability of materials.
- Mechanical Property Degradation: Decrease in mechanical properties.
Mechanisms of Irradiation Damage
- Types of Radiation: Includes energetic neutrons, ions, and electrons that displace atoms.
- Primary Knock-on Atom (PKA): An energetic particle that displaces other atoms, leading to a phenomenon called secondary knock-on atoms (SKAs).
- Displacement Cascade: Sequential atomic displacements caused by ballistic collisions.
Irradiation-Induced Microstructure Changes
- Point Defect Accumulation: Point defects such as vacancies and interstitials accumulate in the material.
- Dislocation Loop Formation: Formation of dislocation loops as a result of defects.
- Effects on Microstructure: Example observations include voids, precipitates, solute segregation, and helium bubbles at grain boundaries.
- Typical scales of defects: 50 nm.
Effects of Irradiation on Material Properties
- Hardening & Embrittlement: Increased strength coupled with reduced ductility in materials.
- Swelling: Void formation leads to macroscopic expansion of the material.
- Phases Instability: Phase transformations can occur as a result of radiation-induced changes.
- Reduction in Thermal Conductivity: The presence of defects scatters phonons, leading to lower heat transport efficiency.
Mitigating Irradiation Damage
- Material Selection:
- High-purity metals (e.g., tungsten, molybdenum) are preferred for their resistance to irradiation damage.
- Radiation-resistant ceramics (e.g., SiC, ZrO₂) are advantageous in this context.
- Self-healing materials: Alloys specifically designed to recombine defects post-damage.
- Temperature Control: Maintaining favorable conditions can support defect recombination.
- Ion Irradiation Testing: Conducting tests simulating radiation damage can aid in material screening for vulnerabilities.