Neutron Energy Spectrum Normalization for Cargo Inspection
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Solution Overview
Problem
Current radiation detectors capable of detecting gamma and neutron radiation struggle to provide detailed information about the nature of a neutron source or material interacting with radiation, especially in complex environments like freight or cargo containers, where distinguishing between different radiation sources and materials is challenging.
Innovation Solution
A method involving a radiation detector that produces neutron energy spectra, normalizes these spectra using parameters like gamma count rates, and compares them to known spectra from a database to identify the radiation source or material, allowing for classification and characterization of neutron sources and materials.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Reliability
If radiation detectors are used to detect gamma and neutron radiation simultaneously, then the capability to detect both radiation types is improved, but the ability to obtain detailed information about the nature of the radiation source deteriorates
Solution Approach 1:
The patent segments the radiation detection process into distinct energy spectrum analysis components. By dividing the neutron energy spectrum into different energy ranges and analyzing each segment separately, the system can extract specific characteristics of the radiation source that would be lost in a combined measurement, thereby resolving the contradiction between simultaneous detection and source characterization.
Solution Approach 2:
The patent utilizes parameter changes by analyzing the energy spectrum at multiple energy levels and comparing spectral shapes. By changing the analysis parameter from simple count rates to energy-dependent spectral parameters, the system maintains reliable detection while gaining detailed source identification capabilities through spectral fingerprinting.
2Loss of information
If neutron energy spectra are measured and analyzed, then information about the radiation source is improved, but the complexity of the measurement and analysis process increases
Solution Approach 1:
The patent applies preliminary action by pre-calculating and storing reference neutron energy spectra for various known radiation sources in a database. This preliminary preparation allows the measurement system to simply compare acquired spectra against the pre-stored references, significantly reducing the complexity of real-time analysis while maintaining high source identification accuracy.
Solution Approach 2:
The patent uses copying by creating spectral fingerprints from measured neutron energy distributions and comparing them against copied reference spectra from the database. This approach simplifies the analysis complexity by transforming complex spectral analysis into a pattern matching process, where the system copies characteristics from reference data to identify unknown sources.
3Measurement precision
If normalization of energy spectra is performed using gamma count rates, then the accuracy of source identification is improved, but the requirement for additional measurements increases
Solution Approach 1:
The patent merges the detection of gamma and neutron radiation into a single integrated measurement process. By combining both radiation type detections and using gamma count rates for neutron spectrum normalization, the system achieves high identification accuracy without requiring separate measurement campaigns, thereby maintaining productivity while improving precision.
Solution Approach 2:
The patent applies universality by designing a detection system that performs multiple functions simultaneously: detecting gamma radiation, detecting neutron radiation, and using the gamma data to normalize the neutron spectrum for improved source identification. This multi-functional approach eliminates the need for additional dedicated measurements, maintaining measurement efficiency while enhancing accuracy.
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
Enables accurate identification and characterization of neutron sources and materials by distinguishing between different radiation sources and analyzing materials interacting with radiation, enhancing sensitivity and providing detailed information for applications such as cargo inspection and nuclear analysis.
Implementation Method 1
Radiation detectors based on noble gas scintillation have the capability of simultaneously detecting gamma and neutron radiation
Data Source
AI summary
A method for obtaining information about an unknown neutron source or an unknown material interacting with a known neutron source comprises the steps of: (a) providing a radiation detector capable of delivering a neutron energy information allowing the production of response histogram(s) as a function of neutron energy, (b) measuring with said radiation detector neutrons being emitted from said unknown neutron source or from said unknown material, (c) deriving from said measured neutrons a neutron energy spectrum, especially in form of a histogram, (d) normalizing said energy spectrum or histogram relative to a parameter or set of parameters derived from the measurement of a different variable, (e) comparing said normalized energy spectrum or histogram with known energy spectra or histograms, and (f) drawing conclusions on the basis of said comparison about the nature of the unknown neutron source or unknown material.