CN1032833C - Neutron and gamma-ray radiation shielding material - Google Patents
Neutron and gamma-ray radiation shielding material Download PDFInfo
- Publication number
- CN1032833C CN1032833C CN 92114783 CN92114783A CN1032833C CN 1032833 C CN1032833 C CN 1032833C CN 92114783 CN92114783 CN 92114783 CN 92114783 A CN92114783 A CN 92114783A CN 1032833 C CN1032833 C CN 1032833C
- Authority
- CN
- China
- Prior art keywords
- gamma
- neutron
- shielding material
- ray radiation
- coupling agent
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Fee Related
Links
Landscapes
- Compositions Of Macromolecular Compounds (AREA)
Abstract
The present invention relates to a shielding material for neutrons and gamma rays, which is composed of any one or multiple kinds of polyethylene and polypropylene series polymer, fast neutron moderator, slow neutron absorber, a gamma ray radiation shielding substance and titanate or silane coupling agent, wherein the fast neutron moderator is at lest one of atomic compound of graphite or a dysprosium containing element; the slow neutron absorber is at least one of atomic compound of a boron, lithium or gadolinium containing element; the gamma ray radiation shielding substance is the atomic simple substance of heavy metal element containing lead, bismuth, barium, etc. or at least one of the compound of the atomic simple substance. The content of the fast neutron moderator is from 1% to 40%; the content of the slow neutron absorbent is from 1% to 9%; the content of the gamma ray radiation shielding substance is from 5% to 40%; the content of the coupling agent is from 0.5% to 3%; the surplus content is moulding substance.
Description
The present invention relates to a kind of neutron and gamma-ray radiation shielding material of mouldable moulding.
Along with the widespread use of nuclear radiation, employed radioactive source kind is more and more, and pattern is variation gradually, and source strength is also increasing.Particularly the first class of employed radioactivity prospecting in use needs roving radioactive source in the position in source in the exploration of image-stone oil, human body is pressed close to radioactive source and is easy to health is damaged when picking and placeing, and also makes the operating personnel produce a kind of nervous psychology simultaneously and is prone to accidents.In order to prevent that human body from coming to harm, guarantee the safety of operation, use the shielding protection instrument of making by radiation shielding material pick and place with the moving radiographic source be necessary.But, the shielding properties of existing neutron and gamma-ray radiation shielding material is single, the safety appliance of making can not shield neutron and gamma-rays radiation simultaneously, the fast neutron shielding properties of particularly existing neutron irradiation shielding material is relatively poor, so the appliance load of making is big, heaviness is unfavorable for using.
The purpose of this invention is to provide a kind of have simultaneously neutron irradiation and gamma-ray radiation shielding performance, the various radioactive source apparatus of picking and placeing are made in mouldable moulding, shielding properties is good, and the appliance load of making is light, neutron of being convenient to manipulate and gamma-ray radiation shielding material.
Neutron and gamma-ray radiation shielding material molded adopt in high radiation-resistant high density polyethylene of hydrogen atom density and the polypropylene series polymkeric substance any one or multiple.
The slow neutron absorbing agent adopts in boron carbide, boron nitride, boric acid, boron oxide, lithium fluoride, lithium bromide, lithium carbonate or gadolinium oxide, gadolinium carbonate and the Digadolinium trisulfate one or more, and gamma ray shielding adopts one or more in lead, massicot, lead octoate, lead acetate, bismuth oxide, bismuthic oxide, bismuth chloride and the barium sulphate.
The dispersion of shielding material in molded for the benefit of with mix, employed coupling agent is one or more compounds in titanate ester or the silane coupling agent.
In order to make neutron and gamma-ray radiation shielding material have good shielding properties, be added with fast neutron moderator in the shielding material, the fast neutron moderator that uses is in graphite or dysprosium carbonate, dysprosia, dysprosium chloride and the dysprosium nitrate one or more.
The becoming to be grouped into and be of neutron and gamma-ray radiation shielding material: fast neutron moderator is that 1-40% (potpourri is heavy) slow neutron absorbing agent is that 1 one 9% (potpourri is heavy), gamma ray shielding agent are 5-40% (potpourri is heavy), coupling agent is 0.5-3% (potpourri is heavy), and surplus is a molded.
In order to guarantee that shielding material has good stable radiation shield performance and excellent physical and mechanical properties and material quality, the comparatively ideal composition of neutron and gamma-ray radiation shielding material is: fast neutron moderator is that 2-20% (mixture weight) slow neutron absorbing agent is 2-8% (mixture weight), the gamma ray shielding agent is 10-20% (potpourri is heavy), and coupling agent is that 1-2.5% (potpourri is heavy) surplus is a molded.
When utilizing neutron provided by the invention and gamma-ray radiation shielding material to make apparatus, after taking by weighing material in each material ratio it is mixed, melting mixing is once made the molding material that mixes to twice in the twin-screw mixer machine then, utilizes molding material can moldedly make required apparatus.
The fast neutron that neutron and gamma-ray radiation shielding material are emitted radioactive source carries out slowing down and is together absorbed by the slow neutron absorbing agent in the material with slow neutron that radioactive source is emitted; thereby improved neutron irradiation shielding protection performance; neutron and the gamma-ray radiation shielding that can simultaneously radioactive source be emitted when using neutron and x radiation x shielding apparatus moving radiographic source; can reduce the thickness of apparatus; reduce the weight of apparatus, be convenient to manipulate.
Embodiment 1
Polypropylene (M130-40) 71 parts (weight), dysprosium carbonate, dysprosia, any one or multiple 10 parts (weight) in dysprosium chloride or the dysprosium nitrate, 8 parts of boron carbides (weight), 10 parts in barium sulphate (weight), 1 part of titanate coupling agent (weight), above-mentioned mixing of materials is evenly after twin-screw mixer machine mixing a pelletizing to the secondary, various mixtures of materials evenly distribute in the pelletizing after tested, polypropylene is external phase, be made into molded pick and place the radioactive source apparatus after, when picking and placeing oil radioactivity well logging probe, measure, radiation shield rate to 18 Curie's americium beryllium neutron source neutrons is 58-63%, gamma ray shielding rate 31-33%, testing tool is that Britain produces MK-7 type neutron dose equivalent rates instrument and PDRI type gamma-rays dose equivalent rate instrument, source rod axis and source active centre are 30 ° to the detector line of centres angle during test, 1 meter of detector centre distance source active centre.
Embodiment 2:
Tygon (MI is 26) 75 parts (weight), graphite 2 minutes (weight), carbonic acid boron, in boron nitride, boron oxide, boric acid, lithium bromide, lithium carbonate, gadolinium oxide, Digadolinium trisulfate or the gadolinium carbonate any one or multiple 2 parts (weight), 20 parts in lead powder (weight), titanate coupling agent 1 part (weight), make by the condition of embodiment 1 and method and to pick and place radioactive source apparatus, the radioactive source that adopts embodiment 1 and testing tool and condition is measured, the neutron irradiation shielding rate is 45-60%, and the gamma ray shielding rate is 40 one 52%.
Embodiment 3:
Tygon (M11.9) 59 (weight), dysprosia 20 parts of (weight), lithium bromide 5 parts of (weight), lead powder, massicot, lead octoate, lead acetate, bismuth oxide, bismuthic oxide, 15 parts of in bismuth chloride and the barium sulphate etc. one or more (weight), 1 part of silane coupling agent (weight), make by the condition of embodiment 1 and method and to pick and place the source apparatus, adopt radioactive source testing tool and the condition of embodiment 1 to measure, the neutron irradiation shielding rate is 59-61%, and the gamma ray shielding rate is 35-48%.
Claims (2)
1, a kind of neutron and sub-x radiation x shielding material, the molding material is a high density polyethylene, at least a in the polypropylene series polymkeric substance, the slow neutron absorbing agent is a boron carbide, boron nitride, boric acid, boron oxide, boron fluoride, lithium bromide, lithium carbonate, gadolinium oxide, carbonic acid rolls, at least a in the Digadolinium trisulfate, the slow neutron absorbing agent is 1-9% of a mixture weight, be generally 2-20%, it is characterized in that fast neutron moderator is arranged, gamma-ray radiation shielding material and coupling agent, fast neutron moderator is a graphite, dysprosia, dysprosium chloride, dysprosium sulfate, at least a in the dysprosium carbonate, the gamma-ray radiation shielding material is plumbous, massicot, lead octoate, lead acetate, bismuth oxide, bismuthic oxide, bismuth chloride, at least a in the bismuth sulfate, coupling agent is a titante coupling agent, at least a in the silane coupling agent, fast neutron moderator is 1-40% of a mixture weight, the gamma-ray radiation shielding material is 5-40% of a mixture weight, coupling agent is 0.5-3% of a mixture weight, and surplus is the molding material.
2, by described neutron of claim 1 and gamma ray shielding material, it is characterized in that said fast neutron moderator is 2-20% of a mixture weight, gamma-ray radiation shielding material is 10-20% of a mixture weight, coupling agent is that potpourri is 1-2.5% of a mixture weight, and surplus is the molding material.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN 92114783 CN1032833C (en) | 1992-12-26 | 1992-12-26 | Neutron and gamma-ray radiation shielding material |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN 92114783 CN1032833C (en) | 1992-12-26 | 1992-12-26 | Neutron and gamma-ray radiation shielding material |
Publications (2)
Publication Number | Publication Date |
---|---|
CN1089055A CN1089055A (en) | 1994-07-06 |
CN1032833C true CN1032833C (en) | 1996-09-18 |
Family
ID=4947105
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN 92114783 Expired - Fee Related CN1032833C (en) | 1992-12-26 | 1992-12-26 | Neutron and gamma-ray radiation shielding material |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN1032833C (en) |
Families Citing this family (32)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US20070102672A1 (en) * | 2004-12-06 | 2007-05-10 | Hamilton Judd D | Ceramic radiation shielding material and method of preparation |
CN100362050C (en) * | 2005-10-21 | 2008-01-16 | 北京市射线应用研究中心 | Composite shielding materials with lead boron polythene material and preparation thereof |
CN100999401A (en) * | 2006-12-28 | 2007-07-18 | 吕迎智 | Protective engineering concrete for weaking proton radiation strength |
CH700461A2 (en) * | 2009-02-17 | 2010-08-31 | Empa | Crooked pneumatic carrier. |
CN101916604A (en) * | 2010-08-02 | 2010-12-15 | 北京富迪创业科技有限公司 | Composite shielding material for preventing neutron radiation and preparation method thereof |
CN102140826A (en) * | 2010-10-27 | 2011-08-03 | 李勇 | Nuclear radiation prevention hollow floor cover |
CN102157214B (en) * | 2010-12-02 | 2016-01-06 | 卜庆革 | Rare earth shielding composite layer silver plating cloth, the clothes of its preparation method and preparation thereof |
CN102708937B (en) * | 2012-05-21 | 2015-01-07 | 北京富迪创业科技有限公司 | Anti-thermal neutron radiation shielding material and preparation method thereof |
CN102664050B (en) * | 2012-05-28 | 2014-10-29 | 丁俊 | Radiation protection material |
CN102719127A (en) * | 2012-07-05 | 2012-10-10 | 南海军 | Anti-neutron irradiation material |
US20140225039A1 (en) * | 2013-02-11 | 2014-08-14 | Industrial Technology Research Institute | Radiation shielding composite material including radiation absorbing material and method for preparing the same |
CN103087522A (en) * | 2013-02-26 | 2013-05-08 | 黑龙江省科学院技术物理研究所 | Radioprotection composite material of nanometer lead borate/polyimide and preparation method thereof |
CN103724760A (en) * | 2013-12-06 | 2014-04-16 | 中国工程物理研究院化工材料研究所 | Neutron-resistant radiation shield plate and preparation method thereof |
CN104119682A (en) * | 2014-07-17 | 2014-10-29 | 中国原子能科学研究院 | Neutron shielding material and preparation method thereof |
CN104310399B (en) * | 2014-10-09 | 2015-12-09 | 东莞理工学院 | A kind of norbide neutron-absorbing body processing technology |
CN105200274B (en) * | 2015-10-26 | 2017-10-03 | 哈尔滨工业大学 | A kind of preparation method of neutron absorber material |
CN105398159B (en) * | 2015-11-19 | 2018-07-24 | 广东阿特斯科技有限公司 | A kind of computer cell phone radiation-proof film |
BR112018075461B1 (en) * | 2016-06-09 | 2023-01-17 | Phoenix Llc. | SYSTEM AND METHOD FOR PERFORMING ACTIVE SCANNING OF A NUCLEAR FUEL STICK |
CN106566013A (en) * | 2016-11-10 | 2017-04-19 | 哈尔滨汉盾辐射防护技术开发有限公司 | Anti-X, gamma ray and neutron radiation shielding material and preparation method thereof |
CN107234794B (en) * | 2017-06-02 | 2019-07-26 | 四川大学 | A kind of preparation method of multi-functional neutron current shielding composite |
CN107118449A (en) * | 2017-06-27 | 2017-09-01 | 苏州菱慧电子科技有限公司 | A kind of elastomeric material of resistance to nuclear radiation |
CN107722425A (en) * | 2017-10-27 | 2018-02-23 | 镇江奥特氟科技有限公司 | A kind of composite particulate material and radiant panel of the radiation of high-intensity shielding neutron gamma |
CN107573569A (en) * | 2017-10-27 | 2018-01-12 | 镇江奥特氟科技有限公司 | A kind of composite particulate material and radiant panel of high-performance shielding neutron gamma radiation |
CN107863173B (en) * | 2017-11-01 | 2019-05-31 | 中国科学院合肥物质科学研究院 | High energy particle degrader part and preparation method thereof |
CN108121005B (en) * | 2017-12-05 | 2019-09-17 | 清华大学 | Utilize the method and neutron dose rate instrument of bromination cerium detector measurement neutron dose rate |
CN108690274B (en) * | 2018-06-20 | 2021-03-12 | 万力轮胎股份有限公司 | Radiation-proof composite latex, preparation method and application thereof, and radiation-proof gloves |
CN111205107A (en) * | 2020-01-15 | 2020-05-29 | 武汉科技大学 | Radiation shielding composite material and preparation method thereof |
CN111572133A (en) * | 2020-05-27 | 2020-08-25 | 成都盛帮密封件股份有限公司 | Flexible material with nuclear radiation protection and electromagnetic shielding functions, and preparation method and application thereof |
CN113185840A (en) * | 2021-04-28 | 2021-07-30 | 禾材高科(苏州)有限公司 | Flexible neutron shielding material and production process thereof |
CN113674889B (en) * | 2021-07-30 | 2023-11-14 | 海南大学 | X-ray radiation protection module and manufacturing method thereof |
CN114479293A (en) * | 2022-01-14 | 2022-05-13 | 四川佳世特橡胶有限公司 | Formula of flexible radiation-proof sealing material for nuclear power |
CN117886357B (en) * | 2023-12-20 | 2024-08-09 | 南京航空航天大学 | Gd for neutron/gamma mixed field radiation protection1–2xCexBixBO3Preparation method, material and application of functional filler |
-
1992
- 1992-12-26 CN CN 92114783 patent/CN1032833C/en not_active Expired - Fee Related
Also Published As
Publication number | Publication date |
---|---|
CN1089055A (en) | 1994-07-06 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN1032833C (en) | Neutron and gamma-ray radiation shielding material | |
US2796529A (en) | Radiation shield | |
Yonezawa et al. | The characteristics of the prompt gamma-ray analyzing system at the neutron beam guides of JRR-3M | |
CN105645865B (en) | A kind of rare earth anti-nuclear radiation mortar and preparation method thereof | |
Makarious et al. | On the utilization of heavy concrete for radiation shielding | |
Klett et al. | The new remcounter LB6411: measurement of neutron ambient dose equivalent H*(10) according to ICRP60 with high sensitivity | |
CN102246245A (en) | Radiation shielding structure composition | |
Akman et al. | Gamma attenuation characteristics of CdTe-Doped polyester composites | |
Usuda et al. | Phoswich detectors for simultaneous counting of α-, β (γ)-rays and neutrons | |
EP4269366A1 (en) | Inorganic composition and fibers and flakes thereof | |
US3705101A (en) | Neutron-absorbing material and method of manufacture | |
Moradgholi et al. | Developing a radiation shield and investigating the mechanical properties of polyethylene-polyester/CdO bilayer composite | |
CN108121005A (en) | Utilize the method and neutron dose rate instrument of bromination cerium detector measurement neutron dose rate | |
Picha et al. | Gamma and neutron attenuation properties of barite-cement mixture | |
JP7559191B2 (en) | Radiation shielding body, method for manufacturing radiation shielding body, and radiation shielding structure | |
Kobayashi et al. | Excellent radiation-resistivity of cerium-doped gadolinium silicate scintillators | |
Aroua et al. | Characterisation of the mixed neutron-gamma fields inside the swiss nuclear power plants by different active systems | |
US4261756A (en) | Lead alloy and granulate concrete containing the same | |
Heaton et al. | Total neutron cross section of carbon from 1 keV to 15 MeV | |
Ridha et al. | Treatment of Radiological Medical Waste Using Concrete Cubic Molds | |
Rimpler | Dose equivalent response of neutron survey meters for several neutron fields | |
Fan et al. | Research and application of nuclear radiation protection materials | |
Eisen et al. | Evaluation of the 63 Cu activation foil for determining the neutron dose in the energy range of 1 eV to 1 MeV | |
Lange et al. | Multi-Element Detectors for Activation Resonance Integral and Resonance Spectrum Measurements | |
Al-Fakeh et al. | Synthesis of Novel Li2O-CuO-Bi2O3-B2O3 Glasses for Radiation Protection: An Experimental and Theoretical Study. Inorganics 2023, 11, 27 |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
C06 | Publication | ||
PB01 | Publication | ||
C10 | Entry into substantive examination | ||
SE01 | Entry into force of request for substantive examination | ||
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 |