Neutron Spectrum Generator Using Scatterer and Material Shell
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Solution Overview
Problem
The increasing cost and limited availability of Californium-252 (Cf-252) as a neutron source for calibrating neutron detectors pose challenges in generating specific neutron spectra, as it is becoming expensive and has a short half-life, necessitating the development of alternative methods to produce calibrated spectra efficiently.
Innovation Solution
A neutron spectrum generator comprising a neutron source, a scatterer, and a material shell with adjustable characteristics such as thickness, angle, and composition to generate specific spectra by measuring responses from different material shells and determining the total fission response by subtracting the differences between these responses, allowing for calibration of neutron detectors to desired spectra without relying on Cf-252.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Measurement precision
If Californium-252 is used as a neutron source for calibration, then a specific fission spectrum can be generated, but the cost increases and availability decreases
Solution Approach 1:
The patent creates a simplified copy of the Cf-252 fission spectrum using a portable generator with a different neutron source (such as Am-Be or Pu-Be) combined with a scatterer and moderator. This copy reproduces the essential spectral characteristics needed for calibration without requiring the expensive and scarce Cf-252 material.
Solution Approach 2:
The invention replaces the expensive, long-lived Cf-252 source with cheaper, shorter-lived alternative neutron sources combined with easily replaceable material components. The portable generator uses readily available materials that can be substituted if degraded, rather than relying on scarce long-lived radioactive isotopes.
2Measurement precision
If Californium-252 is used as a neutron source, then a fission spectrum can be generated, but the half-life limitation reduces operational duration
Solution Approach 1:
The patent changes the physical and chemical parameters of the neutron source system by using alternative isotopes with different half-lives and combining them with moderators and scatterers. This allows tuning the operational duration and spectral characteristics independently, achieving the desired spectrum with extended operational life through material selection rather than relying on Cf-252's fixed properties.
3Quantity of substance
If a portable neutron spectrum generator is developed, then reliance on expensive neutron sources is reduced, but device complexity increases
Solution Approach 1:
The patent divides the neutron spectrum generator into separate functional modules: a neutron source component, a scatterer component, and a moderator component. This segmentation allows each component to be optimized independently, simplified for manufacturing, and easily replaced or adjusted without affecting the entire system, thereby managing complexity while maintaining portability and 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
This approach enables the generation of specific neutron spectra that approximate Cf-252 or other spectra, such as reactor or uranium spectra, efficiently, reducing reliance on expensive neutron sources and extending calibration capabilities to various detector types.
Implementation Method 1
a scatterer positioned in a direct path between the neutron source and a neutron detector
Implementation Method 2
measuring a first response generated responsive to a first material shell of a neutron spectrum generator interacting with a neutron source
Data Source
AI summary
A neutron spectrum generator is disclosed herein including a neutron source, a scatterer positioned in a direct path between the neutron source and a neutron detector, and a material shell configured to have at least one non-uniform characteristic selected from the group consisting of a material, a thickness, a length, an angle, a layer, and combinations thereof to generate a specific spectrum at the neutron detector that is different than the spectrum of the neutron source. A related method includes measuring a first response generated by a first material shell of a neutron spectrum generator interacting with a neutron source, replacing the first material shell with a second material shell, measuring a second response generated by a second material shell of a neutron spectrum generator interacting with the neutron source, and determining a total fission response by determining a difference between the first response and the second response.