Shielded Ion Exchange Vessel for Radionuclide Removal

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Solution Overview

Problem

Current methods for treating radioactive waste at nuclear facilities, such as ion exchange processes, face challenges in efficiently removing radionuclides from large volumes of liquid waste, leading to insufficient capacity and increased waste volumes, along with issues like leaking tanks and high operational costs.

Innovation Solution

A vessel system comprising a shielded housing with an ion exchange chamber, inlet diffuser, and outlet collection header, configured for up-flow operation, using ion exchange media like Crystalline Silicotitanate to remove radionuclides from liquids, and a filtration and ion exchange assembly with rotary microfilters to process radioactive wastewater streams.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Quantity of substance

If ion exchange processes are used to remove radionuclides from large volumes of liquid waste, then the concentration of radionuclides is reduced, but the waste volume increases and treatment capacity becomes insufficient

Engineering Contradiction:
Improveradionuclide concentrationVSAvoidtreatment capacity
Core Design Contradiction:
Quantity of substanceVSProductivity

Solution Approach 1:

The treatment system is divided into multiple ion exchange vessels operating in parallel, with each vessel containing ion exchange media for removing radionuclides. This segmentation allows simultaneous treatment of multiple waste streams, increasing overall treatment capacity while maintaining effective radionuclide removal in each vessel

Inventive Principle:
Principle #1Segmentation

Solution Approach 2:

Ion exchange media serves as an intermediary substance that facilitates the transfer of radionuclides from large volumes of liquid waste into concentrated forms on the media surfaces. The media acts as a bridge between the dilute waste stream and the concentrated waste form, enabling volume reduction while maintaining removal efficiency

Inventive Principle:
Principle #24Intermediary (Mediator)

2Quantity of substance

If conventional ion exchange vessels are used, then radionuclide removal is achieved, but heat dissipation becomes problematic due to insufficient cooling capacity

Engineering Contradiction:
Improveradionuclide removal efficiencyVSAvoidheat dissipation capacity
Core Design Contradiction:
Quantity of substanceVSTemperature

Solution Approach 1:

The vessel design incorporates an internal cooling structure with cooling channels arranged in a three-dimensional configuration within the ion exchange chamber. This adds a thermal management dimension to the conventional ion exchange vessel, allowing heat to be dissipated through the vessel walls and internal structures without interfering with the radionuclide removal process

Inventive Principle:
Principle #17Another dimension (Dimensionality change)

Solution Approach 2:

Coolant flowing through the internal cooling channels acts as an intermediary heat transfer medium, absorbing heat generated during radionuclide removal and transporting it away from the ion exchange media. This intermediary cooling system enables continuous operation by maintaining temperature control

Inventive Principle:
Principle #24Intermediary (Mediator)

3Quantity of substance

If large volumes of liquid waste are processed through conventional treatment facilities, then radionuclides are removed, but operational costs increase significantly

Engineering Contradiction:
Improveradionuclide removalVSAvoidoperational cost
Core Design Contradiction:
Quantity of substanceVSLoss of energy

Solution Approach 1:

The system employs gravity-driven flow through the ion exchange vessels, eliminating the need for energy-intensive pumping between treatment stages. The design allows waste to flow through the treatment media under gravity alone, significantly reducing operational energy costs while maintaining effective radionuclide removal

Inventive Principle:
Principle #25Self-service

Solution Approach 2:

Multiple ion exchange vessels are configured to operate continuously with streamlined flow paths, eliminating idle time between treatment stages. The continuous operation maximizes the utilization of ion exchange media capacity and reduces the frequency of media regeneration or replacement, lowering operational costs

Inventive Principle:
Principle #20Continuity of useful action

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

The system effectively removes radionuclides from large volumes of liquid waste, reducing waste volumes, stabilizing the waste, and providing a more efficient and cost-effective treatment process, while also addressing the challenges of leaking tanks and heat dissipation.

Implementation Method 1

ion exchange processes, such as regenerable ion exchange at Hanford and non-regenerable ion exchange at SRS, to remove various radionuclides

Methodology Applied
Scientific EffectIon exchange: Ion Exchange

Implementation Method 2

an engineered inlet, outlet, and flow distribution system to allow liquid to percolate uniformly through the bed of the medium at a specified flow rate

Methodology Applied
Scientific EffectFluid flow distribution:

Implementation Method 3

outlet collection header disposed in the ion exchange chamber proximate the top surface... A process outlet is in fluid communication with the outlet collection header

Methodology Applied
Scientific EffectFiltration and collection: Filter (physical)

Implementation Method 4

A process inlet is in fluid communication with the inlet diffuser. A process outlet is in fluid communication with the outlet collection header

Methodology Applied
Scientific EffectFluid communication:

Data Source

PatentUS10717660B2Vessel for removing radionuclides from a liquid
Publication Date: 2020.07.21 AVANTECH LLC
  • US10717660B2 patent drawing
  • US10717660B2 patent drawing
  • US10717660B2 patent drawing

AI summary

A vessel for removing radionuclides from a liquid. The vessel comprises a shielded housing comprising an outer shell and an inner shell disposed within the outer shell. The housing defines an ion exchange chamber between the inner and outer shells. The vessel also comprises an inlet fluidly coupled with the ion exchange chamber, the inlet being configured for fluid communication with a source of the liquid, and an outlet fluidly coupled with the ion exchange chamber, the outlet being configured for fluid communication with a destination of the liquid. The vessel further comprises a first fluid passage extending between an exterior of the vessel and the inner shell and a second fluid passage extending between the exterior of the vessel and the inner shell.