BNCT Neutron Filter with Mixed Aluminum Magnesium Fluoride Lithium Fluoride Layers

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Solution Overview

Problem

Current neutron beam sources for boron neutron capture therapy (BNCT) are often located in research reactors, making it inconvenient for medical applications, as they require patients and doctors to travel to these facilities, and existing accelerator-based systems face challenges in optimizing epithermal neutron flux and fast neutron dose rates.

Innovation Solution

A neutron beam source generator comprising an accelerator connected to a beryllium target through a non-circular channel, with a filter composed of a mixed layer of aluminum, magnesium fluoride, and lithium fluoride, and a collimator, optimized by adjusting angles and cross-sectional shapes to enhance epithermal neutron flux while reducing fast neutron dose rates.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Productivity

If an accelerator-based neutron beam source is used, then the device can be integrated into hospital settings and treatment time is reduced, but the epithermal neutron flux is insufficient and fast neutron dose rate is high

Engineering Contradiction:
Improvetreatment timeVSAvoidepithermal neutron flux
Core Design Contradiction:
ProductivityVSQuantity of substance

Solution Approach 1:

The filter is divided into multiple layers with different materials (aluminum, magnesium fluoride, lithium fluoride) and thicknesses. Each layer serves a specific function in moderating neutrons and reducing fast neutron dose, allowing optimization of epithermal neutron flux while maintaining compact hospital-based accelerator integration

Inventive Principle:
Principle #1Segmentation

Solution Approach 2:

The patent optimizes specific parameters including the thickness of each filter layer (aluminum: 5-15 cm, magnesium fluoride: 10-20 cm, lithium fluoride: 5-15 cm), the angle α (10°-30°) between channel and target, and the angle β (30°-60°) between channel and filter normal direction. These parameter changes maximize epithermal neutron flux while minimizing fast neutron dose rate

Inventive Principle:
Principle #35Parameter changes

2Device complexity

If the channel cross-section is circular, then the structure is simple, but the epithermal neutron flux distribution is not optimized

Engineering Contradiction:
Improvechannel structureVSAvoidepithermal neutron flux
Core Design Contradiction:
Device complexityVSQuantity of substance

Solution Approach 1:

The channel cross-section is designed as an asymmetric shape (such as rectangular or elliptical) rather than circular. This asymmetric geometry optimizes the neutron flux distribution by better matching the angular distribution of neutrons from the target, thereby increasing epithermal neutron flux efficiency while maintaining relatively simple construction

Inventive Principle:
Principle #4Asymmetry

3Device complexity

If a single-layer filter is used, then the structure is simple, but the fast neutron dose rate cannot be sufficiently reduced

Engineering Contradiction:
Improvefilter structureVSAvoidfast neutron dose rate
Core Design Contradiction:
Device complexityVSObject-affected harmful factors

Solution Approach 1:

The filter is segmented into three distinct layers, each with specific materials and thicknesses optimized for different functions: aluminum layer for initial neutron moderation, magnesium fluoride layer for further moderation and scattering, and lithium fluoride layer for capturing remaining fast neutrons. This multi-layer segmentation achieves sufficient fast neutron dose rate reduction while maintaining reasonable structural complexity

Inventive Principle:
Principle #1Segmentation

Solution Approach 2:

The filter uses composite material construction combining aluminum, magnesium fluoride, and lithium fluoride in specific thickness ratios. This composite structure leverages the complementary properties of each material to effectively reduce fast neutron dose rate while allowing the filter to be integrated into the compact accelerator-based system

Inventive Principle:
Principle #40Composite materials

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 design achieves a higher epithermal neutron flux and reduced fast neutron dose rates, allowing for more efficient and safer BNCT treatments without the need for patients to undergo invasive skull opening, and can be integrated into hospital settings, reducing costs and treatment time.

Implementation Method 1

an accelerator 11 connected to a beryllium target 15 through a channel 13

Methodology Applied
Scientific EffectNuclear reaction: Nuclear Fission

Implementation Method 2

a filter 17... composed of 1 part by volume of magnesium fluoride, 0.25 to 1 parts by volume of aluminum, and 0.003 to 0.02 parts by volume of lithium fluoride

Methodology Applied
Scientific EffectNeutron moderation: Scattering

Implementation Method 3

a mixed layer of aluminum, magnesium fluoride, and lithium fluoride

Methodology Applied
Scientific EffectNeutron absorption: Absorption (physical)

Data Source

PatentUS11109476B2Filter
Publication Date: 2021.08.31 HERON NEUTRON MEDICAL CORP
  • US11109476B2 patent drawing
  • US11109476B2 patent drawing
  • US11109476B2 patent drawing

AI summary

A filter is provided. The filter includes a mixed layer. The mixed layer includes aluminum, magnesium fluoride, and lithium fluoride. The mixed layer is composed of 1 part by volume of magnesium fluoride, 0.25 to 1 parts by volume of aluminum, and 0.003 to 0.02 parts by volume of lithium fluoride.