Uranium Target Phase Control for Basic Solution Solubility
Find Innovative SolutionsGenerate Solutions
Solution Overview
Problem
Current methods for producing low-enriched uranium targets for extracting radioactive Mo-99 result in low uranium densities, making them inefficient and generating excessive waste, as they are not soluble in basic solutions, leading to challenges in nuclear proliferation and waste management.
Innovation Solution
A method involving the preparation of a conjugate with a matrix and a uranium target green compact, followed by thermo-mechanical treatment at 530° C. to 600° C. during hot rolling, which changes the U or UAl2 phase to UAl3 or UAl4, allowing the uranium target to be dissolved in a basic solution without shape deformation.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Productivity
If highly enriched uranium target (90% or higher) is used to increase productivity of Mo-99, then productivity is improved, but nuclear proliferation risk increases and waste management becomes more difficult
Solution Approach 1:
The patent changes the enrichment parameter of uranium from high enrichment (90% or higher) to low enrichment (20% or less), thereby reducing nuclear proliferation risk while maintaining Mo-99 productivity through compensated increases in uranium total content and optimization of target density and composition
2Object-affected harmful factors
If low-enriched uranium target (20% or less) is used to reduce nuclear proliferation risk, then nuclear proliferation risk is reduced, but Mo-99 production amount decreases due to reduced U-235 content
Solution Approach 1:
The patent compensates for the reduced U-235 content by increasing the total uranium content and optimizing the target density through controlled phase composition (UAl3 and UAl4 phases with specific Al content), thereby maintaining Mo-99 production levels despite using low-enriched uranium
Solution Approach 2:
The patent creates a composite target structure consisting of uranium-aluminum alloy particles dispersed in a metal matrix, where the aluminum content is specifically controlled to form desired intermetallic phases that enhance both density and solubility properties
3Volume of stationary object
If metal U phase is used in the target, then target density is improved, but solubility in basic solution deteriorates, requiring nitric acid dissolution that generates liquid radioactive waste
Solution Approach 1:
The patent changes the chemical phase composition from metallic U phase to uranium-aluminum intermetallic phases (UAl3 and UAl4) by controlling aluminum content and heat treatment parameters, thereby achieving both high density and complete solubility in basic solution without generating liquid radioactive waste
Solution Approach 2:
The patent develops a composite material system where uranium-aluminum alloy particles with specific phase composition are embedded in a metal matrix, creating a target that combines high density with enhanced chemical reactivity toward basic solutions
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 increases the uranium density to 3.0-10.0 gU/cm3, enhancing the extraction yield of radioactive Mo-99 while reducing waste and preventing nuclear proliferation by using low-enriched uranium, which is more easily handled and stored.
Implementation Method 1
performing thermo-mechanical treatment through additional heat treatment at 530° C. to 600° C. during a hot rolling pass in a process of hot-rolling the conjugate
Data Source
AI summary
Disclosed are a method of manufacturing a uranium target, the method including (a) a step of preparing a conjugate including a matrix and a uranium target green compact formed in the matrix; and (b) a step of performing thermo-mechanical treatment through additional heat treatment at 530° C. to 600° C. during a hot rolling pass in a process of hot-rolling the conjugate, and a method of extracting radioactive Mo-99 using the uranium target.


