LiF Shielded Dosimeter Container for Neutron Interference
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Solution Overview
Problem
Current dosimeters face challenges in accurately measuring gamma radiation dosage in neutron radiation environments due to interference from neutron radiation, leading to complex procedures and larger device sizes, and existing shielding materials may emit gamma radiation, affecting measurement accuracy.
Innovation Solution
A dosimeter container with a housing portion for a radiation dosage measuring device and a shield portion made of a LiF sintered body that blocks neutron radiation while allowing gamma radiation to be measured, using a 6LiF sintered body with a relative density of 83% to 90% to enhance neutron shielding and reduce device size.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Measurement precision
If a lead filter is used to block gamma radiation, then gamma radiation measurement accuracy is improved, but the device size increases and procedures become complicated
Solution Approach 1:
The patent extracts the neutron radiation blocking function from the gamma radiation measurement system by using a boron-containing polymer composition that selectively absorbs neutron radiation while allowing gamma radiation to pass through to the dosimeter, eliminating the need for complex lead filters and dual-detector setups
Solution Approach 2:
The patent employs a composite material consisting of boron compounds (such as boron carbide or boron nitride) embedded in a polymer matrix, combining the neutron-absorbing properties of boron with the structural and shielding properties of the polymer to create an effective neutron filter that is compact and simple
2Object-affected harmful factors
If lead or lead alloy is used as shielding material, then gamma radiation blocking is improved, but the material itself emits gamma radiation due to radioactivation
Solution Approach 1:
The patent replaces expensive, radioactivating lead shielding with a boron-containing polymer composition that does not undergo significant radioactivation, effectively using a simpler, non-problematic material to achieve the same shielding function without the harmful side effects
Solution Approach 2:
The patent changes the material composition parameter from lead-based to boron-polymer-based, fundamentally altering the interaction characteristics with neutron and gamma radiation to eliminate radioactivation issues while maintaining effective neutron shielding
3Object-affected harmful factors
If neutron radiation shielding thickness is increased, then neutron radiation blocking is improved, but the device size and weight increase
Solution Approach 1:
The patent uses a composite material where boron compounds are dispersed in a polymer matrix, creating a lightweight yet highly effective neutron shielding layer that blocks neutron radiation without requiring large thickness or excessive weight
Solution Approach 2:
The patent applies neutron shielding locally at the dosimeter surface using a thin layer of boron-containing polymer composition, providing sufficient neutron protection at the measurement point without requiring thick, heavy shielding throughout the entire device
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 solution improves measurement accuracy and downsizes the dosimeter apparatus by effectively blocking neutron radiation and transmitting gamma radiation, simplifying dosage calculation procedures and reducing radiation exposure effects.
Implementation Method 1
a shield portion surrounding the housing portion and including at least a LiF sintered body, the LiF sintered body transmitting the predetermined radiation to be measured with the radiation dosage measuring device, but blocking neutron radiation
Data Source
AI summary
A dosimeter container comprising a housing portion and a shield portion that surrounds the housing portion is provided. The housing portion houses a radiation dosage measuring device for measuring a dosage of predetermined radiation other than neutron radiation. The shield portion is composed of a member made of a material that transmits predetermined radiation and shields neutron radiation. The shield portion is a LiF sintered body, in particular, a 6LiF sintered body. Further, the shield portion includes at least two or more shield portion components (a body portion and a lid portion), in which adjacent members can abutt against each other. The housing portion is same size as or larger than the size of the radiation dosage measuring device; and the housing portion extends over the entirety of the components. The dosimeter container is preferably used as a dosage measuring body having a radiation dosage measuring device stored in the housing portion.