Uranium Fuel Particle Coating for Fission Gas Retention

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Solution Overview

Problem

Current methods for manufacturing U(Mo) nuclear fuel particles result in the formation of an interaction layer with the Al matrix under irradiation, leading to poor fission gas retention and swelling of fuel plates, which is not adequately addressed by silicon addition, especially at higher power densities.

Innovation Solution

A method involving physical vapour deposition to apply a coating layer with neutron poisons and inhibitor elements onto uranium-based fuel particles, allowing for homogeneous distribution and minimizing interaction with the matrix, thereby preventing the formation of detrimental interaction layers.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Quantity of substance

If U(Mo) particles are used as fuel in dispersion fuel plates or rods, then the fuel can be fabricated with lower enrichment, but an interaction layer forms with the Al matrix under irradiation leading to poor fission gas retention and swelling

Engineering Contradiction:
Improveuranium loadingVSAvoidfission gas retention
Core Design Contradiction:
Quantity of substanceVSReliability

Solution Approach 1:

A coating layer comprising inhibitor elements (such as Si, Zr, Nb, Mo, Al, Ti, As, Mg, Ge, Sn, Pb, Bi, Se, Sb or Te) is applied to the U(Mo) particle surface to act as an intermediary barrier between the fuel particle and the Al matrix. This coating prevents direct interaction between the U(Mo) particles and the Al matrix under irradiation, thereby maintaining fission gas retention while allowing the use of lower enrichment uranium loading in the fuel.

Inventive Principle:
Principle #24Intermediary (Mediator)

2Reliability

If Si is added to the Al matrix to improve interaction layer behavior, then some improvement is achieved, but it does not provide a complete solution particularly for higher power densities

Engineering Contradiction:
Improveinteraction layer stabilityVSAvoidapplicability at higher power densities
Core Design Contradiction:
ReliabilityVSAdaptability or versatility

Solution Approach 1:

Instead of uniformly adding Si to the entire Al matrix, the invention applies inhibitor elements locally as a coating layer directly on the U(Mo) particle surface. This localized approach provides targeted protection at the fuel-matrix interface where interaction occurs, achieving effective interaction layer stability control that works across a broader range of power densities without requiring bulk matrix modification.

Inventive Principle:
Principle #3Local quality

3Quantity of substance

If neutron poisons are incorporated by blending powders in the matrix, then reactivity can be fine-tuned, but this method is less appropriate for LEU based fuels requiring higher uranium loadings

Engineering Contradiction:
Improveuranium loadingVSAvoidneutron poison incorporation
Core Design Contradiction:
Quantity of substanceVSEase of manufacture

Solution Approach 1:

The invention segments the neutron poison incorporation by applying it as a coating layer on the U(Mo) particle surface rather than blending powder throughout the matrix. This segmented approach allows precise control of neutron poison distribution at the particle level, enabling effective reactivity fine-tuning in LEU-based fuels with higher uranium loadings while simplifying the manufacturing process compared to uniform powder blending.

Inventive Principle:
Principle #1Segmentation

Applied Scientific Principles

This section explains which scientific principles are used to turn an abstract innovation direction into a practical engineering solution.

Function Achieved in This Case

This approach enables efficient and flexible coating of fuel particles with neutron poisons and inhibitors, enhancing fission gas retention and preventing swelling, while maintaining the stability of the fuel under irradiation across various power densities.

Implementation Method 1

providing at least one physical vapour deposited coating layer surrounding the fuel particle core

Methodology Applied
Scientific EffectPhysical vapour deposition: Physical Vapour Deposition

Data Source

PatentUS9472310B2Coated nuclear reactor fuel particles
Publication Date: 2016.10.18 SCK CEN
  • US9472310B2 patent drawing
  • US9472310B2 patent drawing

AI summary

A method is described for producing nuclear fuel products, including the steps of receiving metallic or intermetallic uranium-based fuel particle cores, providing at least one physical vapour deposited coating layer surrounding the fuel particle core and embedding the nuclear fuel particles in a matrix so as to form a powder mixture of matrix material and coated fuel particles. The at least one physical vapour deposited coating layer may include inhibitors of inhibiting, stabilizing and/or reducing interaction between metallic and intermetallic uranium-based fuel particles cores and the matrix wherein the fuel particles typically may be embedded. The deposited coating layer may include neutron poisons.