Radionuclide Source Container With Shielding For Sealed Transport
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Solution Overview
Problem
Conventional radionuclide generators are inefficient and costly to transport due to the need to ship entire generators, which can decay during shipment and generate gaseous progeny radionuclides, and existing containers are ill-suited for containing these materials.
Innovation Solution
A radionuclide source transport container with a housing, radiation shielding, and a sealable internal volume designed to receive a radionuclide source holder, featuring a lid and lid lock to maintain a sealed configuration, minimizing radiation exposure and preventing gas emission during transport.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Reliability
If entire radionuclide generators are transported, then the radionuclide source is protected and contained, but the transport cost increases and decay during shipment occurs
Solution Approach 1:
The invention separates the radionuclide source holder from the generator system, transporting only the essential source component rather than the entire generator. This segmentation reduces transport time and cost while maintaining source containment through the specialized container with radiation shielding and sealing mechanisms.
Solution Approach 2:
The radionuclide source holder is extracted from the complete generator system for separate transport. This extraction allows the source to be transported in a optimized container that provides necessary containment without the bulk and complexity of the full generator, thereby reducing transport time and associated losses.
2Reliability
If entire generators are transported, then the radionuclide source is secure, but the cost increases
Solution Approach 1:
By segmenting the transport requirement to only the radionuclide source holder rather than the entire generator, the invention reduces transport volume and associated costs while maintaining adequate containment through the purpose-designed container with radiation shielding and sealing features.
Solution Approach 2:
Extracting the radionuclide source holder from the complete generator system enables transport of a smaller, less expensive-to-transport component that still requires reliable containment, thus reducing overall transport cost while maintaining source security.
3Duration of action of moving object
If radionuclide sources with longer half-lives are used, then transport time can be extended, but radiation exposure increases
Solution Approach 1:
The container provides localized radiation shielding at critical areas where radiation exposure could be harmful, allowing longer transport durations with extended half-life sources. The shielding is applied specifically where needed rather than uniformly, enabling extended transport while controlling radiation exposure to acceptable levels.
Solution Approach 2:
The radiation shielding materials in the container act as intermediaries between the radionuclide source and the external environment, absorbing and attenuating radiation during transport. This intermediary protection enables the use of longer half-life sources for extended transport durations while maintaining safe radiation exposure levels.
4Device complexity
If conventional containers are used, then transport is simple, but gas leakage occurs
Solution Approach 1:
The invention converts the potential harm of gas generation from radionuclide decay into a contained scenario by providing sealed containers with pressure relief mechanisms. The gas is captured and controlled within the container system rather than being released, transforming a harmful emission into a managed byproduct that can be safely handled.
Solution Approach 2:
The sealed container structure with specialized seals and pressure relief mechanisms acts as an intermediary barrier between the radionuclide source and the external environment. This intermediary structure prevents direct gas emission while providing controlled pathways for pressure management, thus eliminating harmful gas leakage while maintaining container integrity.
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
Facilitates efficient and cost-effective shipment of radionuclide sources by reducing the need to transport entire generators, allowing for longer half-life materials and minimizing radiation exposure and gas leakage.
Implementation Method 1
a first radiation shielding disposed in the housing; an internal volume formed in the radiation shielding within the housing
Implementation Method 2
a lid seal configured to form a seal between the lid and the housing when the lid is attached to the housing
Implementation Method 3
a housing seal configured to form a seal between radionuclide source holder and the housing to seal the internal volume when the radionuclide source holder is disposed therein
Data Source
AI summary
Some aspects of the present disclosure are generally related to systems and related methods for transporting radionuclide source materials. In some embodiments, a radionuclide source transport container includes a housing with a radiation shielding disposed therein and where the radiation shielding includes an internal volume disposed therein. A distal portion of a radionuclide source holder may be inserted through an opening of the housing into the internal volume. The radionuclide source holder may be supported in a desired pose within the internal volume. In some embodiments, the system includes a lid configured to be selectively attached to the housing as well as a lid seal configured to form a seal between the lid and the housing and/or a seal configured to form a seal between the radionuclide source holder and the housing to seal the internal volume relative to the surrounding environment.