Modular Radiation Shielding Walls for High-Energy Neutron Attenuation
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Solution Overview
Problem
Conventional radiation shielding for proton and heavy ion facilities is costly, time-consuming, and inefficient due to the need for thick concrete structures that become radioactive and require complex decommissioning, while existing modular solutions are inadequate for high-energy neutron shielding.
Innovation Solution
A modular shielding system using non-structural, granular materials with specific atomic numbers for optimized neutron attenuation, allowing for easier installation, removal, and reduced activation, comprising multiple barriers with different compositions to handle a broad spectrum of radiation energies.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Reliability
If thick concrete structures are used for shielding, then radiation attenuation is improved, but construction time and cost increase
Solution Approach 1:
The shielding structure is divided into modular panels that can be pre-fabricated and assembled on-site. Each panel contains integrated shielding material (such as borated polyethylene, concrete, or steel) separated from the structural components, allowing parallel fabrication and simplified assembly, thereby reducing construction time while maintaining required attenuation levels.
Solution Approach 2:
The invention uses composite shielding structures combining multiple materials (steel for structure, concrete for attenuation, borated polyethylene for neutron shielding) in integrated panels. This composite approach optimizes the shielding efficiency per unit thickness, reducing the overall volume and construction time compared to traditional homogeneous concrete structures.
2Reliability
If thick concrete structures are used for shielding, then radiation attenuation is improved, but decommissioning complexity increases
Solution Approach 1:
By segmenting the shielding into removable panels with separated structural and shielding components, the system enables selective removal of shielding material during decommissioning while leaving the structural framework intact. This dramatically simplifies decommissioning compared to monolithic concrete structures that require complete demolition.
Solution Approach 2:
The shielding material is extracted as a separate, removable component from the structural system. Panels can be detached and removed without damaging the building structure, allowing for straightforward decommissioning or reconfiguration of the facility.
3Reliability
If conventional shielding materials are used, then radiation shielding is provided, but material activation increases
Solution Approach 1:
Different shielding materials are applied locally based on the specific radiation type and energy level in each area. For example, borated polyethylene is used where neutron shielding is needed, while lighter materials are used in areas with primarily photon radiation, minimizing unnecessary activation throughout the structure.
Solution Approach 2:
The use of composite materials with lower atomic number components (such as polyethylene and boron compounds) reduces neutron activation compared to traditional heavy concrete and steel structures, while still providing equivalent shielding performance through optimized material composition and configuration.
4Ease of operation
If modular shielding systems are used, then installation ease is improved, but shielding effectiveness for high-energy neutrons deteriorates
Solution Approach 1:
The modular panels incorporate composite shielding materials including borated polyethylene, concrete, and steel in optimized combinations that maintain high neutron attenuation capability while preserving modularity for easy installation and reconfiguration.
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 effective neutron shielding with reduced long-term activation, easier installation and decommissioning, and optimized attenuation across various energy levels, minimizing space and cost requirements.
Implementation Method 1
radiation shielding fill material positioned between the first radiation shielding wall and the second radiation shielding wall forming a first barrier
Implementation Method 2
optimized neutron attenuation
Data Source
Figure 1A
Figure 1B
Figure 2
AI summary
The present disclosure, in an embodiment, is a facility that includes a device configured to generate a beam having an energy range of 5 MeV to 500 MeV, a first radiation shielding wall surrounding the device, a second radiation shielding wall surrounding the first radiation shielding wall, radiation shielding fill material positioned between the first radiation shielding wall and the second radiation shielding wall forming a first barrier. In embodiments, the radiation shielding fill material includes at least fifty percent by weight of an element having an atomic number from 12 to 83, and a thickness of the first barrier is 0.5 meter to 6 meters.