CN2194511Y - Device for measuring shielding property of anti-radiation of neutron - Google Patents
Device for measuring shielding property of anti-radiation of neutron Download PDFInfo
- Publication number
- CN2194511Y CN2194511Y CN 94208221 CN94208221U CN2194511Y CN 2194511 Y CN2194511 Y CN 2194511Y CN 94208221 CN94208221 CN 94208221 CN 94208221 U CN94208221 U CN 94208221U CN 2194511 Y CN2194511 Y CN 2194511Y
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- neutron
- neutron source
- paraffin
- collimating apparatus
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Abstract
The utility model relates to a device for measuring the shielding property of anti-neutron radiation, which is composed of a paraffin pile 1, a californium neutron source, a guide conduit 3, an inner collimator, an outer collimator 6, a shadow cone 7 and a detector 8. The californium neutron source is installed in the guide conduit 3 and inserted in the paraffin pile 1 which has an opening 1 whose depth reaches the guide conduit 3 and the neutron source, the inner collimator 4 which is provided with a central through hole is arranged in the opening, the middle of the outer collimator 6 is provided with a through hole whose inlet is aligned to the central through hole of the inner collimator 4 and whose outlet can be inserted by the minor diameter end of the shadow cone 7, and the detector 8 is situated at the back of the major diameter end of the shadow cone. The utility model can be used for measuring the weakened coefficients of neutron fluence and neutron dosage.
Description
The utility model relates to the device of the shielding properties of measuring anti-neutron irradiation shielding material.
So far we also do not see the report of the measurement mechanism that official seal nuclear radiation material shielding properties is arranged.At present, for the shielding properties of the anti-neutron irradiation of test material, need to use nuclear reactor, its defective is: because of reactor is difficult for moving, so test can only be carried out on reactor; The collimating aperture of drawing neutron beam because of reactor generally is immutable, and so just the size to measured material has certain limitation; The neutron irradiation that produces because of reactor is subjected to multiple factor affecting again, so its poor stability.
In view of this, the utility model will provide a kind of device of measuring the shielding properties of anti-neutron irradiation shielding material, and it can measure the weakening coefficient of neutron fluence, neutron dose.
The purpose of this utility model is achieved in that a kind of device of measuring anti-neutron irradiation shielding material shielding properties is made up of paraffin heap, isotope neutron source, neutron source conduit, interior collimating apparatus, outer collimating apparatus, shadow cone body and detector.Said isotope neutron source is contained in the said neutron source conduit and inserts in the said paraffin heap; Said paraffin heap has a dark opening that reaches said neutron source conduit, the interior collimating apparatus of laying the band central through hole in this opening; The hole is opened in the centre of said outer collimating apparatus, and its inlet is aimed at the through hole of said interior collimating apparatus, and its outlet can be inserted for the miner diameter end of said shadow cone body; Said detector is positioned at after the bigger diameter end of said shadow cone body.Isotope neutron source 2 is a californium neutron source.
Below in conjunction with drawings and Examples the utility model is described in detail.
Fig. 1 is a structural representation of the present utility model.
As shown in FIG., the utility model is made up of paraffin heap 1, isotope neutron source 2, neutron source conduit 3, interior collimating apparatus 4, cylindrical outer collimating apparatus 6, shadow cone body 7 and detector 8.In order to shield neutron and γ radiation better, the paraffin heap adopts double-layer structure: internal layer is a weighted cement; Skin adds a small amount of borax by paraffin and forms.Californium neutron source is contained in the neutron source conduit 3 and inserts in the paraffin heap 1, paraffin heap have the opening 1 of a dark and neutron source conduit 3 ', lay the interior collimating apparatus 4 of band central through hole in this opening, the hole is opened in the centre of outer collimating apparatus 6, the through hole of collimating apparatus 4 in its inlet is aimed at, its outlet can be inserted for the miner diameter end of shadow cone body 7, and 8 of detectors are positioned at after the bigger diameter end of shadow cone body 7.Interior collimating apparatus 4 and outer collimating apparatus 6 add a small amount of borax by paraffin and constitute.
The length of paraffin collimating apparatus is not less than 500mm, and its shape also can be made according to the shape of measured material, and for ease of carrying and operation, it can be made up of some removable components.
Californium neutron source is put in the bottom of neutron source conduit 3 at ordinary times.During measurement, californium neutron source is mentioned the central through hole place of interior collimating apparatus 4, detected materials 5 is tightly placed the outside of interior collimating apparatus 4, collimating apparatus 4, outer collimating apparatus 6 and detector 8 are on same axis in putting in regular turn, after this particle counting value N0 and N in the time of can recording unshielded material and shielding material is arranged by detector 8, the multiple exit that the miner diameter end of shadow cone body 7 is inserted outer collimating apparatus, sample-out count value N0b and Nb in the time of then can recording unshielded material again and shielding material is arranged.Just can calculate the weakening coefficient f of neutron fluence or dosage like this by following formula:
f＝（N0－N0b）／（N－Nb）
The utility model has the advantages that:
1. device adopts isotope neutron source, compares with the neutron that reactor, accelerator produce, have stable radiation, easy and simple to handle, be not subjected to the advantages such as many factors affect, so the degree of accuracy of measuring can improve greatly; In the californium neutron source that adopts and other the isotope Component is compared, and specific activity height, gamma-rays is few, neutron energy spectrum is known advantage are arranged again;
2. the interior collimater 4 that is placed in the paraffin heap opening can be taken out, and therefore can select the interior collimater of different pore size to adapt to the size of detected materials; And if in interior collimater, add the moderator (such as paraffin) of different-thickness, just can obtain the Neutron Radiation Field of different power spectrums, and available theoretical calculation method is known the neutron irradiation power spectrum after the slowing down more definitely;
3. owing between detected materials and the detection instrument outer collimating apparatus is housed, the therefore influence that can deduct background exactly improves measuring accuracy.
4. according to the size of selected californium neutron source,, can suitably select the size of paraffin heap for use, be convenient to move the paraffin heap like this to realize on-the-spot test by the requirement of protection.
Claims (3)
1, a kind of device of measuring the shielding properties of anti-neutron irradiation material, it has paraffin heap (1), isotope neutron source (2) and detector (8), it is characterized in that: it also comprises neutron source conduit (3), interior collimating apparatus (4), outer collimating apparatus (6) and shadow cone body (7), said isotope neutron source (2) is contained in the said neutron source conduit (3) and inserts in the said paraffin heap (1), said paraffin heap (1) has a dark opening (1 ') that reaches said neutron source conduit (3), said interior collimating apparatus (4) is opened central through hole and is placed in this opening (1 '), the hole is opened in the centre of said outer collimating apparatus (6), its inlet is aimed at the central through hole of said interior collimating apparatus (4), its outlet can be inserted for the miner diameter end of said shadow cone body (7), and said detector (8) is positioned at after the bigger diameter end of said shadow cone body (7).
2, the device of the anti-neutron irradiation material shielding performance of measurement according to claim 1 is characterized in that said isotope neutron source (2) is californium neutron source.
3, the device of the anti-neutron irradiation material shielding performance of measurement according to claim 1 and 2, it is two-layer to it is characterized in that said paraffin heap (1) is divided into, and its internal layer is a weighted cement, and its skin adds borax by paraffin and forms.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN 94208221 CN2194511Y (en) | 1994-05-05 | 1994-05-05 | Device for measuring shielding property of anti-radiation of neutron |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN 94208221 CN2194511Y (en) | 1994-05-05 | 1994-05-05 | Device for measuring shielding property of anti-radiation of neutron |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN2194511Y true CN2194511Y (en) | 1995-04-12 |
Family
ID=33826299
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN 94208221 Expired - Fee Related CN2194511Y (en) | 1994-05-05 | 1994-05-05 | Device for measuring shielding property of anti-radiation of neutron |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN2194511Y (en) |
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101901636A (en) * | 2010-07-22 | 2010-12-01 | 中国原子能科学研究院 | Burnup measuring system for spent fuel assembly |
| CN102280149A (en) * | 2011-06-28 | 2011-12-14 | 中国原子能科学研究院 | Neutron photography detection device and detection method for nuclear fuel rod of pressurized water reactor |
| CN105092609A (en) * | 2014-05-16 | 2015-11-25 | 中国核动力研究设计院 | Radiation protective door shielding performance test device and method thereof |
| CN106970095A (en) * | 2016-01-14 | 2017-07-21 | 西安核设备有限公司 | A kind of method that use reference block method detects spent fuel transport container gamma shielding performance |
| CN107561104A (en) * | 2017-09-08 | 2018-01-09 | 中国原子能科学研究院 | A kind of equipment for nuclear power plant's boron aluminum alloy materials neutron-absorbing performance detection |
| CN108107062A (en) * | 2017-12-14 | 2018-06-01 | 东莞理工学院 | A kind of detection device of neutron radiation shield concrete |
| CN108333192A (en) * | 2018-01-25 | 2018-07-27 | 中国科学院高能物理研究所 | A kind of coarse collimator in rear end for neutron scattering |
| CN108802069A (en) * | 2017-05-05 | 2018-11-13 | 中国辐射防护研究院 | The detection device of shielding material shielding properties |
| CN109747042A (en) * | 2017-12-14 | 2019-05-14 | 东莞理工学院 | A kind of radiation shield concrete slurry collocation mechanism of neutron research that can be detected |
| CN111399028A (en) * | 2020-03-19 | 2020-07-10 | 哈尔滨工程大学 | Neutron terminal of multipurpose |
-
1994
- 1994-05-05 CN CN 94208221 patent/CN2194511Y/en not_active Expired - Fee Related
Cited By (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101901636B (en) * | 2010-07-22 | 2012-12-19 | 中国原子能科学研究院 | Burnup measuring system for spent fuel assembly |
| CN101901636A (en) * | 2010-07-22 | 2010-12-01 | 中国原子能科学研究院 | Burnup measuring system for spent fuel assembly |
| CN102280149A (en) * | 2011-06-28 | 2011-12-14 | 中国原子能科学研究院 | Neutron photography detection device and detection method for nuclear fuel rod of pressurized water reactor |
| CN105092609A (en) * | 2014-05-16 | 2015-11-25 | 中国核动力研究设计院 | Radiation protective door shielding performance test device and method thereof |
| CN106970095A (en) * | 2016-01-14 | 2017-07-21 | 西安核设备有限公司 | A kind of method that use reference block method detects spent fuel transport container gamma shielding performance |
| CN106970095B (en) * | 2016-01-14 | 2019-10-18 | 西安核设备有限公司 | A method of spent fuel transport container gamma shielding performance is detected with reference block method |
| CN108802069A (en) * | 2017-05-05 | 2018-11-13 | 中国辐射防护研究院 | The detection device of shielding material shielding properties |
| CN107561104A (en) * | 2017-09-08 | 2018-01-09 | 中国原子能科学研究院 | A kind of equipment for nuclear power plant's boron aluminum alloy materials neutron-absorbing performance detection |
| CN108107062A (en) * | 2017-12-14 | 2018-06-01 | 东莞理工学院 | A kind of detection device of neutron radiation shield concrete |
| CN109747042A (en) * | 2017-12-14 | 2019-05-14 | 东莞理工学院 | A kind of radiation shield concrete slurry collocation mechanism of neutron research that can be detected |
| CN109747042B (en) * | 2017-12-14 | 2020-08-07 | 东莞理工学院 | Radiation-proof concrete paste configuration mechanism capable of detecting neutron research |
| CN108333192A (en) * | 2018-01-25 | 2018-07-27 | 中国科学院高能物理研究所 | A kind of coarse collimator in rear end for neutron scattering |
| CN111399028A (en) * | 2020-03-19 | 2020-07-10 | 哈尔滨工程大学 | Neutron terminal of multipurpose |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| C19 | Lapse of patent right due to non-payment of the annual fee | ||
| CF01 | Termination of patent right due to non-payment of annual fee |