Resin-in-pulp radionuclide separation from ore slurry

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Solution Overview

Problem

Current hydrometallurgical methods for separating radionuclides from ores and tailings are costly and inefficient, requiring multiple stages and high energy consumption, with existing processes failing to effectively reduce radionuclide content to safe levels, posing health and environmental risks.

Innovation Solution

A method involving acid leaching to liberate radionuclides onto the surface of ore particles followed by a resin-in-pulp process using ion exchange resins, which selectively adsorb radionuclides, allowing for their separation from other solids, thereby reducing radionuclide content effectively.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Reliability

If high-temperature hydrometallurgical leach process is used to remove radionuclides, then radionuclide removal efficiency is improved, but capital cost and energy requirements increase significantly

Engineering Contradiction:
Improveradionuclide removal efficiencyVSAvoidenergy requirements
Core Design Contradiction:
ReliabilityVSUse of energy by moving object

Solution Approach 1:

The patent changes the temperature parameter from high-temperature (160-240°C) to low-temperature (20-100°C) operation, making the process more energy-efficient while maintaining effective radionuclide removal through the use of specialized lixiviants designed to work at atmospheric conditions

Inventive Principle:
Principle #35Parameter changes

Solution Approach 2:

The patent employs strong oxidizing agents (nitric acid, ferric sulfate, or hydrogen peroxide) in the lixiviant composition to enhance the leaching efficiency at low temperatures, allowing effective radionuclide removal without requiring high energy input for heating

Inventive Principle:
Principle #38Strong oxidants (Accelerated oxidation)

2Reliability

If alkanesulfonic acid is used in low-temperature leach process, then radionuclide removal effectiveness is improved, but operating cost increases due to high acid cost

Engineering Contradiction:
Improveradionuclide removal effectivenessVSAvoidoperating cost
Core Design Contradiction:
ReliabilityVSLoss of energy

Solution Approach 1:

The patent replaces expensive alkanesulfonic acid with cheaper, readily available mineral acids (sulphuric acid, hydrochloric acid, nitric acid) combined with oxidizing agents, creating a cost-effective lixiviant that achieves similar radionuclide removal effectiveness without the high operating costs of specialized organic acids

Inventive Principle:
Principle #27Cheap short-living objects (Disposable)

Solution Approach 2:

The patent creates a composite lixiviant system combining mineral acids with oxidizing agents (nitric acid, ferric sulfate, or hydrogen peroxide), which together provide both the acidity and oxidation power needed for effective radionuclide removal, replacing the need for expensive single-component alkanesulfonic acid

Inventive Principle:
Principle #40Composite materials

3Reliability

If multiple stages of leaching are used to reduce radionuclides, then radionuclide reduction to safe levels is improved, but process cost increases

Engineering Contradiction:
Improveradionuclide reduction to safe levelsVSAvoidprocess complexity
Core Design Contradiction:
ReliabilityVSDevice complexity

Solution Approach 1:

The patent uses an optimized single-stage leaching process with enhanced lixiviant composition (mineral acid plus oxidizing agent) that achieves sufficient radionuclide removal to safe levels in one pass, avoiding the need for multiple sequential leaching stages while maintaining effectiveness

Inventive Principle:
Principle #16Partial or excessive action

4Reliability

If hydrochloric acid is used for leaching, then radionuclide dissolution is improved, but gangue mineral dissolution increases causing contamination

Engineering Contradiction:
Improveradionuclide dissolutionVSAvoidgangue mineral dissolution
Core Design Contradiction:
ReliabilityVSObject-generated harmful factors

Solution Approach 1:

The patent changes the chemical composition of the lixiviant by combining mineral acids with specific oxidizing agents, which alters the dissolution mechanism to preferentially attack radionuclide-bearing minerals while leaving gangue minerals intact, reducing unwanted contamination

Inventive Principle:
Principle #35Parameter changes

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 significantly reduces radionuclide content in ores and tailings, providing a cost-effective and efficient method for occupational and environmental safety, with the ability to recover valuable metals from the treated residues.

Implementation Method 1

forming a pulp or slurry comprising the ore, ore concentrate or tailings or a mixture or two or more thereof from step (a), water or an aqueous solution, and an ion exchange resin to cause the radionuclides to load onto the resin

Methodology Applied
Scientific EffectIon exchange: Ion Exchange

Implementation Method 2

Hydrometallurgical leaching chemically liberates metals from solid materials. Leaching is the starting point for most hydrometallurgical processes. The chief objective of leaching processes is to selectively dissolve a maximum amount of the element or compound of interest.

Methodology Applied
Scientific EffectLeaching: Solvation

Data Source

PatentUS20240263274A1Method for separating radionuclides from ores, ore concentrates, and tailings
Publication Date: 2024.08.08 UNIQUEST PTY LTD
  • US20240263274A1 patent drawing

AI summary

A method for separating radionuclides from ores, ore concentrates, and tailings or mixtures of two or more thereof comprising the steps of (a) providing an ore, ore concentrate, or tailings, or a mixture of two or more thereof in which radionuclides have been liberated onto surfaces of particles of the ore, ore concentrate or tailings or mixtures of two or more thereof, (b) forming a pulp or slurry comprising the ore, ore concentrate or tailings or a mixture or two or more thereof from step (a), water or an aqueous solution, and an ion exchange resin to cause the radionuclides to load onto the resin, and (c) separating the resin from other solids present in the pulp or slurry.