CN109061712A - A kind of cladding waste measuring device - Google Patents
A kind of cladding waste measuring device Download PDFInfo
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- CN109061712A CN109061712A CN201810895979.1A CN201810895979A CN109061712A CN 109061712 A CN109061712 A CN 109061712A CN 201810895979 A CN201810895979 A CN 201810895979A CN 109061712 A CN109061712 A CN 109061712A
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- cladding waste
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/24—Measuring radiation intensity with semiconductor detectors
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
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Abstract
The invention belongs to cladding waste uranium plutonium content measurement technical fields, more particularly to a kind of cladding waste measuring device, the uranium plutonium content in cladding waste for measuring irradiated fuel assembly generation, it is equipped with including internal in upright tubbiness, accommodate the measurement main body (1) of the measurement chamber (3) of measurement object (4), an accelerator for neutron production (5) and several proportional counter tubes (10) are equipped with inside the measurement main body (1), it further include the gamma detection device that measurement can be moved up and down along the external side of measurement main body (1), the measurement object (4) includes the cladding waste.The present apparatus realizes the measurement and analysis to uranium plutonium content in cladding waste, by providing the parameters such as the uranium plutonium content (U, Pu) and the corresponding α activity that accurately and quickly measure in cladding waste, the level of resources utilization that the links such as spentnuclear fuel post-processing, waste processing disposition can be effectively improved, generates preferable economic benefit.
Description
Technical field
The invention belongs to cladding waste uranium plutonium content measurement technical fields, and in particular to a kind of cladding waste measuring device.
Background technique
The nuclear fuels such as the Pu239 containing the U235, generation that burn incompletely in spentnuclear fuel and some fission products and transuranium member
Element, cladding waste are the residues after clipped irradiated fuel assembly, acidleach and cleaning.The cladding waste that various countries have manufactured and designed at present
Measuring device, and applied in each post-processing pilot plant and commercial big factory, the useless packet of current newest several reprocessing plants
Shell measuring device includes six institutes of UP3 factory, THORP factory of Britain, Japan of France etc..Wherein, French UP3 factory, which uses, source neutron
Measurement method, using Cf252 as inquiry source.THORP factory of Britain, which uses, source neutron challenger method and the analysis side high-resolution γ
Method.Six, Japan is mainly to be improved according to French related process.2002 or so, one moral of China's pilot plant import
The cladding waste measuring device CAMOS of state, which employs the methods for having source neutron and passive neutron measurement technology to combine, and use
For water as slow body, Cf252 increases two ionisation chambers as γ as neutron detector as neutron source, fission chamber is induced
Horizontal monitoring and amendment.
Summary of the invention
With the fast development of China's core cause, the accumulation of spentnuclear fuel is increasing, has carried out related weary combustion in succession thus
Expect reprocessing plant construction and technical study work.For this reason, it is necessary to establish the technological approaches of uranium plutonium content measurement in cladding waste, lead to
The parameters such as uranium plutonium content and the corresponding α activity for providing and accurately and quickly measuring in cladding waste are provided, can be effectively improved weary
The level of resources utilization of the links such as fuel post-processing, waste processing disposition, generates preferable economic benefit.
To achieve the above objectives, the technical solution adopted by the present invention is that a kind of cladding waste measuring device, for measuring weary combustion
Expect the uranium plutonium content in the cladding waste of component generation, wherein be equipped with survey in upright tubbiness, accommodating measurement object including internal
The measurement main body of chamber is measured, the measurement body interior is equipped with an accelerator for neutron production and several proportional counter tubes, and further including can
The gamma detection device of measurement is moved up and down along the measurement body exterior side, the measurement object includes the useless packet
Shell.
Further, the accelerator for neutron production is active accelerator for neutron production.
Further, the measurement main body is made of different material layer, can measurement object described in slowing down emitted neutron,
It reduces the influence for the gamma ray that the measurement object is emitted and reduces the influence of environmental neutron.
Further, the material layer for constituting the measurement main body includes: the first stainless steel layer, lead screen from the inside to the outside
Body, the first polyethylene layer, graphite linings, cadmium piece, the second polyethylene layer, the second stainless steel layer.
Further, the proportional counter tube is embedded in first polyethylene layer, along the axial direction point of the measurement chamber
Dissipate arrangement；The accelerator for neutron production is between the lead screen body and the measurement chamber.
Further, the gamma detection device includes high purity germanium detector and the standard that is arranged on the high purity germanium detector
Straight device, the measurement object that the high purity germanium detector can be detected by the collimator in the measurement main body are emitted
Gamma ray.
It further, further include the fluctuating orbit that the measurement body exterior side is set, the fluctuating orbit is equipped with
For setting up the test platform of the gamma detection device, the gamma detection device passes through the test platform and the lifting
Track realization moves up and down measurement.
It further, further include connection and the control for remotely controlling the accelerator for neutron production, high purity germanium detector, fluctuating orbit
Equipment, the control equipment are able to record the measurement result of the accelerator for neutron production, high purity germanium detector.
It further, further include that the intracavitary hanging basket of the measurement is set, the hanging basket is for placing the measurement object.
It further, further include the top cover that the measurement body top is set, the main body of the top cover is made by polyethylene,
Additional stainless steel packaging, for fixing the accelerator for neutron production.
The beneficial effects of the present invention are:
The present apparatus realizes the measurement and analysis to uranium plutonium content in cladding waste, while realizing the neutron moisture to cladding waste
Amount and gamma ray measurement and analysis, by providing the uranium plutonium content (U, Pu) and phase that accurately and quickly measure in cladding waste
The parameters such as the α activity answered can effectively improve the level of resources utilization of the links such as spentnuclear fuel post-processing, waste processing disposition,
Generate preferable economic benefit.
Detailed description of the invention
Fig. 1 is a kind of schematic diagram of cladding waste measuring device described in the specific embodiment of the invention；
In figure: 1- measures main body, 2- top cover, and 3- measures chamber, 4- measurement object, 5- accelerator for neutron production, the detection of 6- HpGe
Device, 7- collimator, 8- test platform, 9- fluctuating orbit, 10- proportional counter tube
Specific embodiment
The invention will be further described with reference to the accompanying drawings and examples.
As shown in Figure 1, a kind of cladding waste measuring device provided by the invention, for measuring the useless packet of irradiated fuel assembly generation
Uranium plutonium content in shell, including measurement main body 1, top cover 2, measurement chamber 3, accelerator for neutron production 5, gamma detection device are (including high-purity
Germanium detector 6, collimator 7), test platform 8, fluctuating orbit 9, proportional counter tube 10, hanging basket, control equipment etc..
The inside of main body 1 is measured equipped with the measurement chamber 3 for accommodating measurement object 4, measurement chamber 3 is in upright tubbiness, measurement
Include measured cladding waste sample in object 4.Measurement main body 1 be made of different material layer, can slowing down measurement object 4 sent out
The influence of the neutron, the influence and reduction environmental neutron that reduce the gamma ray that measurement object 4 is emitted penetrated, is the standard of neutron
It really measures and offer approach is provided and is guaranteed.
The material layer for constituting measurement main body 1 includes: the first stainless steel layer (thickness 0.2cm), lead screen body (thickness from the inside to the outside
Spend 10cm), the first polyethylene layer (thickness 10cm), graphite linings (thickness 4cm), cadmium piece (thickness 0.1cm), the second polyethylene layer
(thickness 4cm), the second stainless steel layer (thickness 0.2cm primarily serves the beautiful effect with fixing internal structure).
Accelerator for neutron production 5 is tubulose (quantity 1), is located between lead screen body and measurement chamber 3, and accelerator for neutron production 5 is to have
Source neutron generator.Proportional counter tube 10 is embedded in the first polyethylene layer, and the axial dispersion along measurement chamber 3 is arranged in measurement chamber
3 outside (interval of proportional counter tube 10, which can be, to be uniformly also possible to unevenly, can satisfy technical indicator)；According to
According to Project Technical index request, the quantity of required proportional counter tube 10 is determined by Monte Carlo simulation calculation method.Here
It is adopted as 92, but not fixed constant can be calculated further by simulation to change number of tubes, as long as or meeting technology
Index request.
The setting of fluctuating orbit 9 is equipped in measurement 1 outside side of main body, fluctuating orbit 9 for setting up gamma detection device
Test platform 8, gamma detection device is realized mobile to along measurement steadily up and down by test platform 8 and fluctuating orbit 9
1 outside side of main body moves up and down measurement.
Gamma detection device includes high purity germanium detector 6 and the collimator 7 that is arranged on high purity germanium detector 6, HpGe
Detector 6 can detect the gamma ray that the measurement object 4 in measurement main body 1 is emitted by collimator 7.
Equipment connection and long-range control accelerator for neutron production 5, high purity germanium detector 6, fluctuating orbit 9 are controlled, equipment energy is controlled
Enough record the measurement result of accelerator for neutron production 5, high purity germanium detector 6.
Hanging basket setting positions in measurement chamber 3 in measurement chamber 3 for placing measurement object 4, and by measurement object 4.
The setting of top cover 2 is made in 1 top of measurement main body, the main body of top cover 2 by polyethylene, and additional stainless steel packaging is used for
Fixed accelerator for neutron production 5.
It is as follows that operating process is implemented in the measurement of cladding waste measuring device provided by the invention:
1) top cover 2 is moved to by designated position using hanging apparatus；
2) measurement object 4 comprising cladding waste sample is transmitted in measurement chamber 3 by 3 upper end of measurement chamber using hanging apparatus
Fixation position；
3) top cover 2 is reapposed in the top of measurement main body 1 using hanging apparatus；
4) after top cover 2 is placed, according to measurement needs, experiment parameter needed for setting controls equipment；
5) after the completion of parameter setting, start neutron and gamma survey；(neutron measurement is surveyed by proportional counter tube 10
Amount)
6) measurement that shift register carries out neutron background is opened；
7) it opens accelerator for neutron production 5 and carries out active neutron measurement, obtain neutron measurement data；
8) after measuring, accelerator for neutron production 5 is closed, and carries out neutron measurement data processing and saves；
9) gamma survey is carried out simultaneously with step 6,7,8, make test platform 7 along lifting by software Command Control Equipment
Steadily lifting measures track 8；
10) it after measuring, carries out data gamma measure and saves；
11) top cover 2 is moved to by designated position using hanging apparatus；
12) use hanging apparatus by measurement object 4 by being transmitted to designated position in measurement chamber 3；
13) measurement process terminates.
Device of the present invention is not limited to embodiment described in specific embodiment, those skilled in the art according to
Technical solution of the present invention obtains other embodiments, also belongs to the scope of the technical innovation of the present invention.
Claims (10)
1. a kind of cladding waste measuring device, the uranium plutonium content in cladding waste for measuring irradiated fuel assembly generation, it is characterized in that:
Including the internal measurement main body (1) for being equipped with measurement chamber (3) in upright tubbiness, accommodating measurement object (4), the measurement main body
(1) internal to be equipped with an accelerator for neutron production (5) and several proportional counter tubes (10), further including can be along the measurement main body
(1) external side moves up and down the gamma detection device of measurement, and the measurement object (4) includes the cladding waste.
2. cladding waste measuring device as described in claim 1, it is characterized in that: the accelerator for neutron production (5) is to have source neutron hair
Raw device.
3. cladding waste measuring device as described in claim 1, it is characterized in that: the measurement main body (1) is by different material layer structure
At, can measurement object (4) described in slowing down emitted neutron, reduce the gamma ray that the measurement object (4) is emitted
Influence and reduce the influence of environmental neutron.
4. cladding waste measuring device as claimed in claim 3, characterized in that constitute the material of measurement main body (1)
Layer includes: the first stainless steel layer, lead screen body, the first polyethylene layer, graphite linings, cadmium piece, the second polyethylene layer, the from the inside to the outside
Two stainless steel layers.
5. cladding waste measuring device as claimed in claim 4, it is characterized in that: the proportional counter tube (10) is embedded in described
In one polyethylene layer, along the axial dispersion arrangement of measurement chamber (3)；The accelerator for neutron production (5) is located at the lead screen body
Between the measurement chamber (3).
6. cladding waste measuring device as described in claim 1, it is characterized in that: the gamma detection device includes HpGe detection
Device (6) and the collimator (7) being arranged on the high purity germanium detector (6), the high purity germanium detector (6) can be by described
The gamma ray that the measurement object (4) in collimator (7) detection measurement main body (1) is emitted.
7. cladding waste measuring device as claimed in claim 6, it is characterized in that: further include setting the measurement main body (1) outside
The fluctuating orbit (9) of portion side, the fluctuating orbit (9) are equipped with the test platform for setting up the gamma detection device
(8), the gamma detection device moves up and down measurement by the test platform (8) and the fluctuating orbit (9) realization.
8. cladding waste measuring device as claimed in claim 7, it is characterized in that: further including that connection is sent out with the neutron is remotely controlled
The control equipment of raw device (5), high purity germanium detector (6), fluctuating orbit (9), the control equipment are able to record the neutron hair
The measurement result of raw device (5), high purity germanium detector (6).
9. cladding waste measuring device as described in claim 1, it is characterized in that: further including being arranged in the measurement chamber (3)
Hanging basket, the hanging basket is for placing the measurement object (4).
10. cladding waste measuring device as described in claim 1, it is characterized in that: further including that setting is pushed up in the measurement main body (1)
The main body of the top cover (2) in portion, the top cover (2) is made by polyethylene, and additional stainless steel packaging occurs for fixing the neutron
Device (5).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810895979.1A CN109061712A (en) | 2018-08-08 | 2018-08-08 | A kind of cladding waste measuring device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810895979.1A CN109061712A (en) | 2018-08-08 | 2018-08-08 | A kind of cladding waste measuring device |
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| CN109061712A true CN109061712A (en) | 2018-12-21 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201810895979.1A Pending CN109061712A (en) | 2018-08-08 | 2018-08-08 | A kind of cladding waste measuring device |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111580150A (en) * | 2020-04-30 | 2020-08-25 | 中国原子能科学研究院 | Barreled nuclear waste detection system |
| CN112764078A (en) * | 2020-12-22 | 2021-05-07 | 中国原子能科学研究院 | Nuclear material measuring device |
| CN114895342A (en) * | 2022-05-20 | 2022-08-12 | 中国原子能科学研究院 | Monitoring system for nuclear critical safety of precipitation reactor |
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111580150A (en) * | 2020-04-30 | 2020-08-25 | 中国原子能科学研究院 | Barreled nuclear waste detection system |
| CN111580150B (en) * | 2020-04-30 | 2022-06-28 | 中国原子能科学研究院 | Barreled nuclear waste detection system |
| CN112764078A (en) * | 2020-12-22 | 2021-05-07 | 中国原子能科学研究院 | Nuclear material measuring device |
| CN112764078B (en) * | 2020-12-22 | 2022-08-09 | 中国原子能科学研究院 | Nuclear material measuring device |
| CN114895342A (en) * | 2022-05-20 | 2022-08-12 | 中国原子能科学研究院 | Monitoring system for nuclear critical safety of precipitation reactor |
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Application publication date: 20181221 |