Radioisotope Generator with Removable Shielding

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Solution Overview

Problem

Conventional radioisotope generators for nuclear medicine require frequent replacement, are bulky and heavy, limiting predictability and reproducibility, and result in significant handling and disposal challenges due to their shielding materials, while also being inflexible in activity levels and having limited radioisotope production capacity.

Innovation Solution

A system comprising a reactor housing made of radioactive shielding material with an internal chromatographic column and a filter module, allowing for customizable and reproducible radioisotope production with a chromatographic column positioned for fluid communication between entry and exit ports, and a delivery vessel for elution, enabling extended use without weekly replacement and reduced handling of shielding materials.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Object-affected harmful factors

If conventional generators use lead shielding materials, then radiation protection is ensured, but the device becomes heavy and bulky, requiring frequent handling and disposal

Engineering Contradiction:
Improveradiation protectionVSAvoidgenerator weight
Core Design Contradiction:
Object-affected harmful factorsVSWeight of moving object

Solution Approach 1:

The patent extracts the shielding function from the generator housing and places it in a separate removable shield. This allows the generator itself to be lightweight and easy to handle, while radiation protection is maintained through the detachable shield that can be positioned as needed during elution procedures

Inventive Principle:
Principle #2Taking out (Extraction)

Solution Approach 2:

The system is divided into separate functional components: the generator unit, the elution system, and the shielding component. This segmentation allows each component to be optimized independently - the generator can be small and portable, while the shield provides adequate protection when in use

Inventive Principle:
Principle #1Segmentation

2Reliability

If conventional generators are replaced bi-weekly, then radioisotope supply is maintained, but manipulation and disposal of heavy generators creates significant toil and waste

Engineering Contradiction:
Improveradioisotope supply continuityVSAvoidgenerator replacement effort
Core Design Contradiction:
ReliabilityVSEase of operation

Solution Approach 1:

The generator system is designed to remain in place at the patient location, eliminating the need for frequent replacement. The long-lived parent isotope allows the generator to service multiple patients over an extended period, and the system is designed for easy disposal at the end of its useful life without requiring complex replacement procedures

Inventive Principle:
Principle #25Self-service

3Ease of manufacture

If conventional generators use fixed activity denominations, then manufacturing is simplified, but flexibility and predictability for customized radioisotope needs are limited

Engineering Contradiction:
Improvegenerator production simplicityVSAvoidactivity level flexibility
Core Design Contradiction:
Ease of manufactureVSAdaptability or versatility

Solution Approach 1:

The system allows dynamic adjustment of activity levels by varying the elution frequency and volume. Rather than manufacturing generators with fixed activities, the same generator can provide different activity levels on demand by controlling how often and how much eluate is collected, providing both manufacturing simplicity and clinical flexibility

Inventive Principle:
Principle #15Dynamics

4Productivity

If conventional generators are designed for standard capacity, then production is efficient, but high activity levels above 19 Ci cannot be provided

Engineering Contradiction:
Improveradioisotope production efficiencyVSAvoidradioisotope activity level
Core Design Contradiction:
ProductivityVSQuantity of substance

Solution Approach 1:

The system overcomes the 19 Ci limitation by changing the physical parameters of the generator design, including the size of the parent isotope loading, the column dimensions, and the elution flow rates. These parameter adjustments allow the system to handle and deliver high activity levels while maintaining efficient production through optimized chromatographic conditions

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

The system provides customized, predictable, and reproducible radioisotope supplies with higher activity levels, reducing the need for frequent generator replacements and handling of heavy shielding materials, while allowing for flexible activity adjustments and extended operation without compromising safety or efficiency.

Implementation Method 1

Most commercial generators use column chromatography, in which Mo-99 is adsorbed onto alumina

Methodology Applied
Scientific EffectAdsorption: Adsorption

Implementation Method 2

Most commercial generators use column chromatography, in which Mo-99 is adsorbed onto alumina. Normal saline solution can be run through a column of immobilized Mo-99 to elute soluble Tc-99m

Methodology Applied
Scientific EffectChromatography: Chromatography

Implementation Method 3

reactor housing that is fabricated from a radioactive shielding material

Methodology Applied
Scientific EffectRadioactive shielding: Absorption (EM radiation)

Implementation Method 4

a filter module that is disposed external to said reactor housing and in fluid communication with said exit port

Methodology Applied
Scientific EffectFiltration: Filter (physical)

Implementation Method 5

Mo-99 has a half-life of 66 hours and can be transported over long distances to radiopharmacies and hospitals where its decay product Tc-99m is used for nuclear medicine diagnostic procedures

Methodology Applied
Scientific EffectRadioactive decay: Radioactive Decay

Data Source

PatentUS7700926B2Systems and methods for radioisotope generation
Publication Date: 2010.04.20 JUBILANT DRAXIMAGE INC
  • US7700926B2 patent drawing
  • US7700926B2 patent drawing
  • US7700926B2 patent drawing

AI summary

Systems and methods are disclosed for producing customized, predictable and reproducible supplies of radioisotopes using, for example, a reactor housing that is fabricated from a radioactive shielding material and has both an internal volume and a surface that comprises an entry port and an exit port, a chromatographic column that is positioned within said internal volume such that a first end of said column is in fluid communication with said entry port and a second end of said column is in fluid communication with said exit port, and a changeable filter module that is disposed external to said reactor housing and in fluid communication with said exit port.