Uranium Target Phase Control for Basic Solution Solubility

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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

VSEngineering 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

Engineering Contradiction:
Improveproductivity of Mo-99VSAvoidnuclear proliferation risk
Core Design Contradiction:
ProductivityVSObject-affected harmful factors

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

Inventive Principle:
Principle #35Parameter changes

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

Engineering Contradiction:
Improvenuclear proliferation riskVSAvoidproduction amount of Mo-99
Core Design Contradiction:
Object-affected harmful factorsVSProductivity

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

Inventive Principle:
Principle #35Parameter changes

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

Inventive Principle:
Principle #40Composite materials

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

Engineering Contradiction:
Improvetarget densityVSAvoidsolubility in basic solution
Core Design Contradiction:
Volume of stationary objectVSEase of manufacture

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

Inventive Principle:
Principle #35Parameter changes

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

Inventive Principle:
Principle #40Composite materials

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

Methodology Applied
Scientific EffectPhase transformation: Phase Change

Data Source

PatentUS11713498B2Method of manufacturing uranium target to be soluble in basic solution and method of extracting radioactive Mo-99 using the same
Publication Date: 2023.08.01 KOREA ATOMIC ENERGY RES INST
  • US11713498B2 patent drawing
  • US11713498B2 patent drawing
  • US11713498B2 patent drawing

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.