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Apparatus and method for neutron detection by capture-gamma calorimetry

A technology of thermal neutrons and neutrons, applied in the field of devices for detecting neutron radiation (preferably thermal (slow) neutrons), which can solve the problems of difficulty in distinguishing charged particle radiation, increasing technical complexity and related costs

Inactive Publication Date: 2012-06-13
前视红外放射有限责任公司
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

It is therefore necessary to measure this single decay very accurately in order to achieve at least reasonable results, thus greatly increasing the technical complexity and associated costs
In addition, it is difficult if not impossible to distinguish charged particle radiation (e.g. charged particle radiation of cosmic origin) with detectors as disclosed by Bell
[0012] In summary, the known medium The sub-detector concept is unmatched by 3 he tube competition

Method used

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  • Apparatus and method for neutron detection by capture-gamma calorimetry
  • Apparatus and method for neutron detection by capture-gamma calorimetry
  • Apparatus and method for neutron detection by capture-gamma calorimetry

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Embodiment Construction

[0046] figure 1 In its lower part a longitudinal cut through an embodiment is shown. The detector 100 and three of its main segments are shown here. Gamma scintillator material 101 mounted on a photodetector 103, preferably a photomultiplier tube or an array of Geiger mode avalanche photodiodes (G-APDs), can be seen. This gamma scintillator material is divided into two parts along its longitudinal axis, and the neutron capture material 102 is arranged between the two parts of the gamma scintillator. The location of the neutron capture material 102 can be clearly seen in the transverse cut through the scintillator material shown in the upper part of the figure.

[0047] The gamma scintillator material is selected in such a way that its neutron capture cross-section for thermal (slow) neutrons is low, thus allowing most neutrons to pass through the scintillator material without neutron capture.

[0048] The neutron capture segment 102 at the center of the detector is a sheet...

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Abstract

The invention relates to an apparatus for detecting neutron radiation, preferably thermal neutrons, comprising at least one first section (102) with a high neutron absorption capability and at least one second section (101) with a low neutron absorption capability, the second section comprising a gamma ray scintillator, the gamma ray scintillator material comprising an inorganic material with an attenuation length of less than 10 cm, preferably less than 5 cm for gamma rays of 5 MeV energy in order to provide for high gamma ray stopping power for energetic gamma rays within the second section, where the material of the first section is selected from a group of materials, releasing the energy deployed in the first section by neutron capture mainly via gamma radiation, and where the second section is surrounding the first section in a way that a substantial portion of the first section is covered by the second section, the apparatus further comprising a light detector (103) 1, optically coupled to the second section in order to detect the amount of light in the second section, the apparatus further comprising an evaluation device coupled to the light detector, said device being able to determine the amount of light, detected by the light detector for one scintillation event, that amount being in a known relation to the energy deployed by gamma radiation in the second section, where the evaluation device is configured to classify detected radiation as neutrons when the measured total gamma energy E (sum) is above 2,614 MeV.

Description

technical field [0001] The present invention relates to a device for detecting neutron radiation, preferably thermal (slow) neutrons, using a gamma ray scintillator for indirect detection. Background technique [0002] Although there is a wide variety of methods and equipment available for neutron detection, it remains common in most applications requiring the most efficient neutron counting at the lowest cost. 3 The main pipe. However, it is expected 3 He is in short supply, making a need for a substitute. [0003] Such alternative detectors are known in the prior art. Knoll, Radiation Detection and Measurement, 3rd Edition, 2000, p. 506 states that all common reactions used to detect neutrons are reactions with the emission of charged particles. More specifically, possible reaction products for detection are recoil nuclei (mainly protons), tritons, alpha particles and fission fragments. However gamma rays following neutron capture reactions are used in some specialize...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01T3/06
CPCG01T3/06
Inventor G.保施C.M.赫尔巴赫J.施泰因
Owner 前视红外放射有限责任公司
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