Moderator-Surrounded Neutron Detection for Low-False-Positive Fissile Sensing

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Solution Overview

Problem

Current neutron detection systems relying on helium-3 are economically unscalable due to shortages and high costs, and suffer from high false positive rates caused by poor gamma-ray energy resolution, limiting their effectiveness in detecting fissile materials like plutonium and highly enriched uranium.

Innovation Solution

A fissile neutron detection system comprising a neutron moderator and thermal neutron detectors with a hydrogen-containing material that transitions high-energy fissile neutrons to low-energy thermal neutrons, captured by active materials like lithium-6 or boron-10, enhancing detection efficiency and reducing false positives through improved gamma-ray rejection.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Reliability

If helium-3 based neutron detection systems are deployed, then neutron detection capability is achieved, but cost and scalability are severely limited due to helium-3 shortages and high costs

Engineering Contradiction:
Improveneutron detection capabilityVSAvoidscalability and cost
Core Design Contradiction:
ReliabilityVSEase of manufacture

Solution Approach 1:

The patent extracts the detection function from helium-3 based systems and implements it using alternative materials (lithium-6, boron-10) that are abundant and cost-effective, thereby eliminating the scalability and cost limitations while preserving neutron detection capability

Inventive Principle:
Principle #2Taking out (Extraction)

Solution Approach 2:

The patent creates a functional copy of the helium-3 detection mechanism using different materials (thermal neutron converters coupled with semiconductor detectors) that achieve the same detection purpose but with improved scalability and reduced cost

Inventive Principle:
Principle #26Copying

2Reliability

If conventional neutron detectors are used, then neutron detection is possible, but false positive rates increase due to poor gamma-ray energy resolution

Engineering Contradiction:
Improvedetection functionVSAvoidgamma-ray energy resolution
Core Design Contradiction:
ReliabilityVSMeasurement precision

Solution Approach 1:

The patent introduces thermal neutron converters (lithium-6, boron-10) as intermediary materials that selectively interact with thermal neutrons through nuclear reactions, producing charged particles that can be detected with high precision while being insensitive to gamma-rays, thereby eliminating false positives

Inventive Principle:
Principle #24Intermediary (Mediator)

Solution Approach 2:

The patent changes the detection parameter from direct gamma-ray energy measurement to nuclear reaction product detection (charged particles from lithium-6 or boron-10 reactions), which provides superior energy resolution and eliminates gamma-ray interference

Inventive Principle:
Principle #35Parameter changes

3Reliability

If detection systems are deployed at multiple locations, then overall security against nuclear threats increases, but the lack of scalable technology limits the evolution of existing systems

Engineering Contradiction:
Improveoverall securityVSAvoidsystem scalability
Core Design Contradiction:
ReliabilityVSAdaptability or versatility

Solution Approach 1:

The patent employs modular detector designs that can be independently deployed at multiple locations (port facilities, transportation hubs, border crossings), with each unit being self-contained and scalable through simple replication rather than requiring complex system evolution

Inventive Principle:
Principle #1Segmentation

Solution Approach 2:

The patent creates universal detection platforms using abundant materials and standardized designs that can be deployed across diverse locations and applications, providing adaptable security coverage that scales with deployment needs rather than being limited by technology evolution constraints

Inventive Principle:
Principle #6Universality (Multi-functionality)

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 achieves high fissile neutron capture efficiency exceeding 50% and low false positive rates, enabling scalable and cost-effective detection of fissile materials while maintaining robustness and longevity for military applications.

Implementation Method 1

Fissile neutrons impinge upon and enter the neutron moderator where the energy level of the fissile neutron is reduced to that of a thermal neutron

Methodology Applied
Scientific EffectNeutron moderation:

Implementation Method 2

The thermal neutron may exit the moderator in any direction. Maximizing the surface area of the neutron moderator that is proximate the neutron detector beneficially improves the reliability and accuracy of the fissile neutron detection system by increasing the percentage of thermal neutrons that exit the neutron moderator and enter the neutron detector

Methodology Applied
Scientific EffectNeutron detection:

Data Source

PatentEP3610301B1Advanced fissile neutron detection system and method
Publication Date: 2024.04.03 SILVERSIDE DETECTORS INC
  • EP3610301B1 patent drawingFigure 1A~1B
  • EP3610301B1 patent drawingFigure 1C~1D
  • EP3610301B1 patent drawingFigure 1E~1F

AI summary

A fissile neutron detection system includes an ionizing thermal neutron detector arrangement including an inner peripheral shape that at least substantially surrounds a moderator region for detecting thermal neutrons that exit the moderator region but is at least generally transparent to the incident fissile neutrons. A moderator is disposed within the moderator region having lateral extents such that any given dimension that bisects the lateral extents includes a length that is greater than any thickness of the moderator arrangement transverse to the lateral extents. The moderator can include major widthwise and major lengthwise lateral extents such that any given dimension across the lengthwise and widthwise lateral extents includes a length that is greater than any thickness of the moderator arrangement transverse to the lateral extents.