Method for carrying out neutron measurement on uranium contents in uranium-containing liquid and achievement device of method

A uranium content and neutron detector technology, applied in the field of nuclear detection/nuclear analysis, can solve the problems of inability to carry out online monitoring of nuclear criticality safety, long analysis process, cumbersome operation, etc., and achieve short measurement time, high analysis accuracy, and responsive fast effect

Active Publication Date: 2017-07-28
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0004] The technical problem to be solved by the present invention is: the existing detection method has the problems of long analysis process, cumbersome operation, and inability to carry out on-line monitoring of nuclear criticality safety. The purpose is to provide a method and its realization The device solves the problems of on-line monitoring of nuclear criticality safety and nuclear material balance calculation, and can realize real-time and on-line measurement of uranium concentration in uranium-containing liquid

Method used

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  • Method for carrying out neutron measurement on uranium contents in uranium-containing liquid and achievement device of method
  • Method for carrying out neutron measurement on uranium contents in uranium-containing liquid and achievement device of method

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Experimental program
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Embodiment 1

[0033] A method for neutronically measuring uranium content in uranium-containing liquids, comprising:

[0034] pass 241 The neutrons emitted by the Am-Be neutron source (average neutron energy 5.0MeV) penetrate the pipe wall and undergo fission reaction with the uranium-containing liquid in the pipe. The neutron count rate N in the pipe is measured by the neutron detector 测 , according to the calculation model N 测 = Φ 热 σ f N U-235 ty, calculate the uranium content N in the pipeline U-235 .

[0035] In the present invention Φ 热 is the average neutron fluence rate in the pipeline, the average neutron fluence rate Φ in the pipeline 热 The calculation method is as follows:

[0036] (1) Inject uranium-containing liquids with different uranium contents of 100mg / L, 500mg / L, 1000mg / L, 2000mg / L, and 5000mg / L into the pipeline respectively, and measure N at corresponding concentrations by neutron detectors 测 ,

[0037] (2) According to the calculation model N 测 = Φ 热 σ f N...

Embodiment 2

[0049] This embodiment provides a device for realizing the method of neutron measurement of uranium content in uranium-containing liquid, and the specific settings are as follows figure 1 As shown, it includes a neutron source 1 installed on the uranium-containing liquid pipeline 10, a neutron detector 3 arranged on the uranium-containing liquid pipeline 10, connected with the neutron detector 3 and based on the calculation model N 测 = Φ 热 σ f N U ty, calculate the uranium content N in the pipeline U The signal processing device, where, N 测 is the neutron count rate detected by the neutron detector 3, Φ 热 is the average neutron fluence rate in the pipeline, σ f is the microscopic section, t is the measurement time, and y is the average number of neutrons released per fission.

[0050] The present invention can directly arrange the neutron source 1, the neutron detector 3 and the signal processing device on the pipeline (point) to be monitored, so that the quantitative de...

Embodiment 3

[0052] The only difference between this embodiment and Embodiment 2 is that this embodiment provides a specific structure of a signal processing device, such as figure 2 Shown; Simultaneously, present embodiment has also increased electronics circuit shielding body 9 and neutron source shielding body 2 on the basis of embodiment 2, as figure 1 shown.

[0053] In the present embodiment, the signal processing device includes a preamplifier 5, an amplifier 6, a discrimination counter 7, and a data processing terminal 8 connected in sequence; the preamplifier 5 is connected with the neutron detector 3, and the preamplifier 5 is Also connected to the power supply 4 that provides energy for the signal processing device, such as figure 2 shown.

[0054] Preamplifier selects the spectrum amplifier module of Canberra 2022 model for use in the present embodiment; Amplifier matches with preamplifier, and screening counter can select Siemens PLC (S7-200) high-speed counter HC4 for use...

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Abstract

The invention discloses a method for carrying out neutron measurement on uranium contents in uranium-containing liquid and an achievement device of the method. The objective of the invention is to solve problems of long analysis processes, tedious operation and failure to carry out safe online monitoring on nuclear borderlines in the current detection methods. The method comprises steps of using neutrons radiated by a neutron source to penetrate through a pipeline wall; allowing neutrons to react with uranium-containing liquid in the pipeline; measuring the neutron counting rate N-measurement in the pipeline through a neutron detector, and calculating the uranium contents NU in the pipeline according to a calculation model shown in the description, wherein the phi heat is the average neutron injection rate in the pipeline, the sigmaf is the micro cross section, the t is the measurement time and the y is the average released neutron number of fission of every time. According to the invention, the method and the device are advantaged by capability of achieving real-time and online measurement on uranium concentration in the uranium-containing liquid.

Description

technical field [0001] The invention relates to the technical field of nuclear detection / nuclear analysis, in particular to a neutron method for measuring uranium content in a uranium-containing liquid and a device for realizing it. Background technique [0002] Fuel element development and spent fuel reprocessing are very important links in the nuclear industry system and the core work of the nuclear fuel cycle. Among them, the chemical conversion of uranium is a key link in the development of fuel microspheres, which provides the necessary fuel phase for the manufacture of fuel veneers, directly affects the progress of the development of fuel elements, and is also related to the closed balance of nuclear materials. Spent fuel reprocessing is the last link of the nuclear industry system, which directly determines the safety of nuclear engineering. [0003] In the technological conversion process of uranium chemical conversion, the uranium concentration value of uranium-con...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01T1/167G01T3/00
CPCG01T1/167G01T3/00
Inventor 赵峰廖志海彭小明邱绍宇乔洪波王占明安身平
Owner NUCLEAR POWER INSTITUTE OF CHINA
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