Integrated neutron-gamma radiation detector with adaptively selected gamma threshold

一种伽马阈值、伽马辐射的技术，应用在辐射的测量、辐射强度测量、X /γ/宇宙辐射测量等方向，能够解决妨碍检测和测量等问题

Inactive Publication Date: 2009-06-10
GENERAL ELECTRIC CO
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

In many field applications, the incident gamma flux may be high enough to generate a significant amount of interaction in neutron sensing components, preventing detection and measurement of possibly concurrently low neutron fluxes

Method used

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  • Integrated neutron-gamma radiation detector with adaptively selected gamma threshold
  • Integrated neutron-gamma radiation detector with adaptively selected gamma threshold
  • Integrated neutron-gamma radiation detector with adaptively selected gamma threshold

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Embodiment Construction

[0014] Referring now to FIG. 1 , an integrated neutron-gamma radiation detector is shown generally at 10 . At one end, the detector 10 includes a neutron moderator 12 comprising a material that slows fast neutrons entering the moderator 12 but allows thermal neutrons and gamma rays to pass easily therethrough. For example, neutron moderator 12 may include hydrogen or the like. The speed reducer 12 includes a cavity 14 lined with a light reflector 16 . Gamma sensing element 18 is disposed within cavity 14 of neutron moderator 12 and is surrounded by light reflector 16 to increase the light efficiency of detector 10 . In one embodiment, the gamma sensing element 18 includes a scintillator crystal that emits photons with a decay time τ when a gamma ray collides with the gamma sensing element 18 . Typical materials for scintillator crystals include, but are not limited to, those from the class of lanthanum halides (LaBr 3 , LaCl 3 , LaI 3 ) crystalline materials with high ene...

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Abstract

The invention relates to an integrated neutron-gamma radiation detector with adaptively selected gamma threshold. The integrated radiation detector (10) having a pulse-mode operating photosensor (24) optically coupled to a gamma sensing element (18) and a neutron sensing element (20) is disclosed. The detector (10) includes a pulse shape and processing electronics package (26) that uses an analogto digital converter (ADC) and a charge to digital converter (QDC) to determine scintillation decay times and classify radiation interactions by radiation type. The pulse shape and processing electronics package (26) determines a maximum gamma energy from the spectrum associated with gamma rays detected by the gamma sensing element (18) to adaptively select a gamma threshold for the neutron sensing element (20). A light pulse attributed to the neutron sensing element (20) is a valid neutron event when the amplitude of the light pulse is above the gamma threshold.

Description

technical field [0001] The teachings herein relate to hand-held detectors of ionizing radiation, and more particularly to detectors that distinguish between gamma and neutron components. Background technique [0002] Detecting radioactive materials, especially those illicitly concealed in the stream of commerce, requires access to a variety of radiation detection equipment. In particular, there is a need in the field for Handheld Radioisotope Identification Devices (HHRIIDs) to quickly determine the presence of specific nuclear material and distinguish it from the presence of medical and industrial radioisotopes, as well as from commonly occurring radioactive materials. One possible embodiment of the HHRIID consists of two optically separated radiation sensors that emit light and are coupled to a common photodetector. The first radiation sensor is a neutron sensing part containing atomic nuclei with a high neutron cross section, such as for example 6 In the chemical compou...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01T3/06G01T1/202
CPCG01T3/06G01T1/1642G01T1/17
Inventor A·伊万S·J·杜克罗斯D·B·麦德维特J·R·威廉斯B·A·克罗蒂尔J·S·戈顿
Owner GENERAL ELECTRIC CO
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