CN203365690U - Neutron measurement device - Google Patents
Neutron measurement device Download PDFInfo
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- CN203365690U CN203365690U CN 201320253449 CN201320253449U CN203365690U CN 203365690 U CN203365690 U CN 203365690U CN 201320253449 CN201320253449 CN 201320253449 CN 201320253449 U CN201320253449 U CN 201320253449U CN 203365690 U CN203365690 U CN 203365690U
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- neutron
- measurement device
- measurement
- neutron measurement
- pail
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Abstract
The utility model, which belongs to the technical field of radioactive waste detection, discloses a neutron measurement device. A main body portion of the device is a semi-cylinder-shaped polyethylene slowing-down body; and one or more <3>He neutron tubes are embedded at one side, approaching a waste bin, of the semi-cylinder, wherein the effective center point heights of the <3>He neutron tubes are consistent with the central height of the water bin. The provided neutron measurement device with the simple structure can be disassembled conveniently; the integrated measurement of the waste bin can be carried out; and measurement of transmissivity of a gamma ray is not influenced.
Description
Technical field
The utility model belongs to radioactive waste detection technique field, is specifically related to the neutron measurement device.
Background technology
Along with the growing growth of nuclear industry, it is large that the nuclear material that nuclear facilities produces or nuclear waste speedup also become rapidly, for support facility material turnover balance, usually need to carry out barrelling to these materials, and to inner radionuclide content Measurement and analysis.
In the standard pail for used dressings in the quantitative measurment of nuclear material or nuclear waste, usually need to adopt and measure its neutron emission rate and come definite kernel material classification or а refuse content, this Project design a set of device of the neutron measurement for 200 liters of barreled materials.
The utility model content
(1) utility model purpose
The utility model provides a kind of can measure and not affect on the neutron emission rate of 200 liters of whole buckets of pail for used dressings the neutron measurement device of gamma-rays transmission measurement.
(2) technical scheme
In order to solve the existing problem of prior art, the technical scheme that the utility model provides is:
The neutron measurement device, the main part of this device is semi-cylindrical tygon slow body, half-cylindrical, near pail for used dressings one side, is embedded with one or more
3the He neutron tube, wherein
3he neutron tube active center point height is consistent with the pail for used dressings centre-height.
Preferably,
3the measuring-signal of He neutron tube transfers to computing machine after multichannel analyzer is processed.
Preferably, the support with roller is equipped with in half-cylindrical poly bottom.
(3) beneficial effect
The neutron measurement device that adopts the utility model to provide, this apparatus structure is simple, easy accessibility, can carry out whole bucket to pail for used dressings and measure, and not affect the gamma-rays transmissivity measurement.
The accompanying drawing explanation
Fig. 1 is neutron measurement device schematic diagram;
1.
3the He neutron tube; 2. tygon slow body; 3. support; 4. roller.
Embodiment
Below in conjunction with specification drawings and specific embodiments, the utility model is further elaborated.
The neutron measurement device, the main part of this device is semi-cylindrical tygon slow body 2, at slow body, near pail for used dressings one side, is embedded with 18
3he neutron tube 1, wherein
3the active center point height of He neutron tube 1 is consistent with the pail for used dressings centre-height.
3the measuring-signal of He neutron tube transfers to computing machine after multichannel analyzer is processed.Support 3 with roller 4 is housed in the bottom of slow body.
While utilizing this neutron measurement device to carry out scale to pail for used dressings, the neutron source of selecting is
252cf, place it in a barrel centre-height position, measures now neutron gross-count rate, and after the deduction background, the nominal value of comparison neutron source, can draw the neutron measurement efficiency of current measuring position.To simultaneously
252cf neutron source along the bucket radial direction one by one measurement point move, each measurement point interval 5cm, and rotation nuclear waste bucket, can obtain auto levelizer to the detection efficiency roomage response on nuclear waste bucket radial direction, its av eff is 5.12%, and each measurement point detection efficiency relative standard deviation is 2.6%.
Same, can from bottom, making progress at the bucket central axis, every 10cm selectes a height, places
252cf neutron source, measure its detection efficiency successively, and the detection efficiency mean value that can obtain on axis is 5.05%, and relative standard deviation is 3%.
Upper planar survey explanation, in 200 liters of nuclear waste buckets of rotation, this mounted point detection efficiency roomage response consistance is better.
Claims (3)
1. the neutron measurement device, is characterized in that, the main part of this device is semi-cylindrical tygon slow body (2), half-cylindrical, near pail for used dressings one side, is embedded with one or more
3he neutron tube (1), wherein
3he neutron tube active center point height is consistent with the pail for used dressings centre-height.
2. neutron measurement device according to claim 1, is characterized in that, described
3the measuring-signal of He neutron tube transfers to computing machine after multichannel analyzer is processed.
3. neutron measurement device according to claim 1, is characterized in that, the support (3) of band roller (4) is equipped with in the bottom of described half-cylindrical tygon slow body.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN 201320253449 CN203365690U (en) | 2013-05-13 | 2013-05-13 | Neutron measurement device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN 201320253449 CN203365690U (en) | 2013-05-13 | 2013-05-13 | Neutron measurement device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN203365690U true CN203365690U (en) | 2013-12-25 |
Family
ID=49813435
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN 201320253449 Expired - Lifetime CN203365690U (en) | 2013-05-13 | 2013-05-13 | Neutron measurement device |
Country Status (1)
| Country | Link |
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| CN (1) | CN203365690U (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108919330A (en) * | 2018-08-08 | 2018-11-30 | 中国原子能科学研究院 | A kind of 1AF feed liquid measuring device |
| CN108919334A (en) * | 2018-08-22 | 2018-11-30 | 中国原子能科学研究院 | A kind of UF6The verification measurement method of uranium quality and abundance in big tank |
| CN109100000A (en) * | 2018-08-22 | 2018-12-28 | 中国原子能科学研究院 | A kind of UF6The verification measuring device and method of uranium quality and abundance in big tank |
| CN109269538A (en) * | 2018-10-16 | 2019-01-25 | 中国海洋石油集团有限公司 | One kind is with brill neutron He3 pipe scale test device |
| CN113484894A (en) * | 2021-06-11 | 2021-10-08 | 中国电子产品可靠性与环境试验研究所（（工业和信息化部电子第五研究所）（中国赛宝实验室）） | Alpha particle emissivity measuring method |
-
2013
- 2013-05-13 CN CN 201320253449 patent/CN203365690U/en not_active Expired - Lifetime
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108919330A (en) * | 2018-08-08 | 2018-11-30 | 中国原子能科学研究院 | A kind of 1AF feed liquid measuring device |
| CN108919334A (en) * | 2018-08-22 | 2018-11-30 | 中国原子能科学研究院 | A kind of UF6The verification measurement method of uranium quality and abundance in big tank |
| CN109100000A (en) * | 2018-08-22 | 2018-12-28 | 中国原子能科学研究院 | A kind of UF6The verification measuring device and method of uranium quality and abundance in big tank |
| CN109100000B (en) * | 2018-08-22 | 2021-08-20 | 中国原子能科学研究院 | UF (ultra filtration factor)6Device and method for verifying and measuring quality and abundance of uranium in large tank |
| CN109269538A (en) * | 2018-10-16 | 2019-01-25 | 中国海洋石油集团有限公司 | One kind is with brill neutron He3 pipe scale test device |
| CN109269538B (en) * | 2018-10-16 | 2021-02-05 | 中国海洋石油集团有限公司 | Measurement-while-drilling neutron He3 tube scale testing device |
| CN113484894A (en) * | 2021-06-11 | 2021-10-08 | 中国电子产品可靠性与环境试验研究所（（工业和信息化部电子第五研究所）（中国赛宝实验室）） | Alpha particle emissivity measuring method |
| CN113484894B (en) * | 2021-06-11 | 2024-01-05 | 中国电子产品可靠性与环境试验研究所（（工业和信息化部电子第五研究所）（中国赛宝实验室）） | Alpha particle emissivity measuring method |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CX01 | Expiry of patent term | ||
| CX01 | Expiry of patent term |
Granted publication date: 20131225 |