CN101302367B - Anti-neutron size putty - Google Patents

Anti-neutron size putty Download PDF

Info

Publication number
CN101302367B
CN101302367B CN2008101164906A CN200810116490A CN101302367B CN 101302367 B CN101302367 B CN 101302367B CN 2008101164906 A CN2008101164906 A CN 2008101164906A CN 200810116490 A CN200810116490 A CN 200810116490A CN 101302367 B CN101302367 B CN 101302367B
Authority
CN
China
Prior art keywords
neutron
putty
shielding
powder
kilograms
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.)
Active
Application number
CN2008101164906A
Other languages
Chinese (zh)
Other versions
CN101302367A (en
Inventor
尚宏忠
曾心苗
郭振涛
鲍矛
王红杰
周成飞
郑金美
张龙
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
BEIJING RAY APPLIED RESEARCH CENTRE
BEIJING FUDI TECHNOLOGY Co Ltd
Original Assignee
BEIJING RAY APPLIED RESEARCH CENTRE
BEIJING FUDI TECHNOLOGY Co Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by BEIJING RAY APPLIED RESEARCH CENTRE, BEIJING FUDI TECHNOLOGY Co Ltd filed Critical BEIJING RAY APPLIED RESEARCH CENTRE
Priority to CN2008101164906A priority Critical patent/CN101302367B/en
Publication of CN101302367A publication Critical patent/CN101302367A/en
Application granted granted Critical
Publication of CN101302367B publication Critical patent/CN101302367B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Abstract

The invention provides a quick dry type neutron-shielding lacquer putty and a method for preparing the same. The quick dry type neutron-shielding lacquer putty is used for filling a hole or an aperture of a neutron radiant point shielding structure in order to reduce the leakage of neutron radiation and improve the whole protective performance of a shielding system. The material is prepared by adopting a coagulant, a neutron moderator, a neutron absorber, a colorant, water and other compositions mixed together. The quick dry type neutron-shielding lacquer putty has good neutron-shielding performance, short drying time, simple structure, convenient construction, strong practicability and good economical benefit.

Description

Anti-neutron size putty
Technical field
The present invention relates to a kind of anti-neutron size putty and preparation method thereof, be used for the shielding protection in all kinds of neutron radiations sources such as isotope neutron source, nuclear reactor, rumbatron.
Background technology
Isotope neutron source, nuclear reactor and accelerator can produce nuclear radiation in operational process, especially the neutron radiation penetrativity is very strong, and operator's health is caused huge threat.General now use iron, lead, polyethylene, paraffin or composite shielding material carry out shielding protection to these source of radiation, these materials are in the process of installing and using, the material junction can stay a little slit, and neutron radiation can be damaged operator by these places, slit, reduces the protection effect of bulk shielding structure greatly.Secondly pipeline and hole road are more around source of radiation, and the void shape irregular that forms on shielding construction adopts existing shielding material to be difficult to accomplish tight radio-protective.In order in construction process, these slits and cavity effectively to be shielded and to protect, adopt and prevent that neutron putty is filled up these slits and the cavity is the obvious and inexpensive method of effect.
Traditional aqueous putty is at normal temperatures because the water velocity of evaporation is slower, putty is longer time of drying, and necessary rapid drying after some particular application requires the putty construction to finish, with the security of assurance equipment and shielding construction, so be badly in need of a kind of rapid drying type neutron shield putty of exploitation on the market.
Summary of the invention
The object of the present invention is to provide a kind of anti-neutron size putty, be used for filling up of neutron emitter shielding system cavity and slit.
Above-mentioned purpose of the present invention reaches by the following technical programs:
A kind of anti-neutron size putty, its component and weight ratio are as follows:
Peptizer: 30~60 parts;
Neutron moderator: 10~40 parts;
Neutron-absorbing material: 5~10 parts;
Tinting material: 5~15 parts;
Water: 20~50 parts.
A kind of preferred version is characterized in that: described peptizer is putty powder, cement or gypsum etc.
A kind of preferred version is characterized in that: described neutron moderator is a polyethylene.
A kind of preferred version is characterized in that: described neutron-absorbing material is szaibelyite, borax, boron powder, norbide, lithium fluoride, gadolinium sesquioxide.
A kind of preferred version is characterized in that: described tinting material is iron oxide black, carbon black.
The production technique of anti-neutron size putty is various solid powders to be mixed in proportion to make putty powder earlier, during construction putty powder and water is in harmonious proportion in proportion use, finishes construction in 1~2h.Water also has the effect of neutron moderator.
Beneficial effect:
Anti-neutron size putty disclosed by the invention, the neutron shield excellent performance, anti-neutron performance is better than the polythene material of stack pile, time of drying is at 3~4h, meet the construction needs, technology is simple, easy construction, can be widely used in the construction aspect of isotropic substance radioactive source, Nuclear power plants, nuclear reactor, accelerator shielding safeguards, have wide economic benefit and good social benefit.
Embodiment
Below in conjunction with specific examples anti-neutron size putty of the present invention is further specified, to help understanding content of the present invention.
Embodiment 1
The anti-neutron size putty of present embodiment is made of following component:
Cement 42.5R:50 kilogram
Polyethylene powder: 30 kilograms
Szaibelyite: 8 kilograms
Iron oxide black: 5 kilograms
Water: 25 kilograms
Peptizer uses the cement 42.5R that sells on the market, with uniform mixing after the solid materials weighing, adds the water of above-mentioned amount during use, can use after mixing.
Embodiment 2
The anti-neutron size putty of present embodiment is made of following component:
Cement 42.5R:60 kilogram
Polyethylene powder: 30 kilograms
Norbide: 10 kilograms
Iron oxide black: 15 kilograms
Water: 35 kilograms
Peptizer uses the cement 42.5R that sells on the market, will put into high speed agitator after the solid materials weighing, and uniform mixing 5min can use.During on-the-spot the use, add the water of above-mentioned amount, mix and to construct.
Embodiment 3
The anti-neutron size putty of present embodiment is made of following component:
821 putty for scraping walls: 45 kilograms
Polyethylene powder: 20 kilograms
Lithium fluoride: 5 kilograms
Iron oxide black: 10 kilograms
Water: 24 kilograms
Peptizer uses 821 putty for scraping walls of selling on the market, will put into high speed agitator after the solid materials weighing, and uniform mixing 5min can use.During on-the-spot the use, add the water of above-mentioned amount during use, mix and to construct.
Embodiment 4
The anti-neutron size putty of present embodiment is made of following component:
821 putty for scraping walls: 30 kilograms
Polyethylene powder: 40 kilograms
Gadolinium sesquioxide: 7 kilograms
Carbon black: 10 kilograms
Water: 26 kilograms
Peptizer uses 821 putty for scraping walls of selling on the market, with uniform mixing after the solid materials weighing, adds the water of above-mentioned amount during use, can use after mixing.
Embodiment 5
The anti-neutron size putty powder of present embodiment is made of following component:
J-5 terra alba: 40 kilograms
Polyethylene powder: 10 kilograms
Borax: 10 kilograms
Carbon black: 12 kilograms
Water: 20 kilograms
Peptizer uses the J-5 terra alba of selling on the market, with uniform mixing after the solid powder weighing, adds the water of above-mentioned amount during use, can use after mixing.
Embodiment 6
The anti-neutron size putty powder of present embodiment is made of following component:
J-5 terra alba: 60 kilograms
Polyethylene powder: 30 kilograms
Boron powder: 10 kilograms
Iron oxide black: 12 kilograms
Water: 50 kilograms
Peptizer uses the J-5 terra alba of selling on the market, with uniform mixing after the solid powder weighing, adds the water of above-mentioned amount during use, can use after mixing.
The effect test:
Prescription with embodiment 2 is made putty, and making thickness is that 4cm, length and width are the sample of 24 * 16cm, carries out the neutron shield performance test according to the mark Q/CYSXY004-2007 of enterprise, adopts 252The Cf neutron emitter adopts 3He proportional counter specimen thermal neutron shielding properties numerical value is 18.10, and the polyethylene board thermal neutron shielding factor of condition of equivalent thickness only is 14.95, and the NEUTRON PROTECTION effect of anti-neutron size putty is better than polythene material under condition of equivalent thickness.
Press the density of GB/T1033-86 specimen, be 1.1g/cm 3
Adopt the visual observation product appearance, product colour is even, no layering, no macrobead.
Anti-neutron size putty integrated performance index is as shown in the table:
Interventions Requested Technical indicator Operative norm
The neutron shield performance (18.10 4cm is thick) Q/CYSXY004-2007
Density >1.0g/cm 3 GB/T1033-86
Product appearance Color even, no layering, no macrobead Visual

Claims (3)

1. anti-neutron size putty, its component and weight ratio are as follows:
Peptizer: 30~60 parts;
Neutron moderator: 10~40 parts;
Neutron-absorbing material: 5~10 parts;
Tinting material: 5~15 parts;
Water: 20~50 parts;
Described peptizer is putty powder, cement or gypsum, and described neutron moderator is a polyethylene, and neutron-absorbing material is szaibelyite, borax, boron powder, norbide, lithium fluoride, gadolinium sesquioxide; Earlier described peptizer, neutron moderator, neutron-absorbing material and tinting material are made anti-neutron size putty powder by described mixed, will prevent again during construction that neutron size putty powder and water use in described ratio mediation, finish construction in 1~2h.
2. anti-neutron size putty as claimed in claim 1 is characterized in that: described tinting material is iron oxide black or carbon black.
3. anti-neutron size putty as claimed in claim 1 is characterized in that: described peptizer is 821 mastic powder for wall, cement 42.5R or J-5 terra alba.
CN2008101164906A 2008-07-10 2008-07-10 Anti-neutron size putty Active CN101302367B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN2008101164906A CN101302367B (en) 2008-07-10 2008-07-10 Anti-neutron size putty

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN2008101164906A CN101302367B (en) 2008-07-10 2008-07-10 Anti-neutron size putty

Publications (2)

Publication Number Publication Date
CN101302367A CN101302367A (en) 2008-11-12
CN101302367B true CN101302367B (en) 2011-03-30

Family

ID=40112479

Family Applications (1)

Application Number Title Priority Date Filing Date
CN2008101164906A Active CN101302367B (en) 2008-07-10 2008-07-10 Anti-neutron size putty

Country Status (1)

Country Link
CN (1) CN101302367B (en)

Families Citing this family (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102485810A (en) * 2009-11-30 2012-06-06 北京市射线应用研究中心 Dual-component low-temperature curing type putty for mixed nuclear radiation environment
CN102140826A (en) * 2010-10-27 2011-08-03 李勇 Nuclear radiation prevention hollow floor cover
CN102214490B (en) * 2011-04-26 2013-05-29 北京大学 Neutron shielding material and manufacturing method thereof
CN103426492B (en) * 2012-05-18 2016-12-14 中国科学院高能物理研究所 Neutron shielding material and preparation technology
CN105542543A (en) * 2016-01-20 2016-05-04 广西丛欣实业有限公司 Radiation-proof putty powder
ES2904361T3 (en) 2017-10-11 2022-04-04 Nippon Light Metal Co Shielding adhesive having neutron shielding properties
CN112900770A (en) * 2021-01-19 2021-06-04 湖南熊熊科技有限公司 Construction method for preventing wall surface from peeling off
CN113149703B (en) * 2021-05-28 2022-08-30 湖北工业大学 Neutron radiation prevention light gypsum board and preparation method thereof
CN115321902B (en) * 2022-08-01 2023-04-14 河北中耐新材料科技有限公司 Anti-cracking radiation-proof concrete for preventing neutron radiation and preparation method thereof

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN1517413A (en) * 2003-01-16 2004-08-04 深圳市海川实业股份有限公司 Anticracking putty inner wall for
JP2007303953A (en) * 2006-05-11 2007-11-22 Fujita Corp Concrete for radiation shielding

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN1517413A (en) * 2003-01-16 2004-08-04 深圳市海川实业股份有限公司 Anticracking putty inner wall for
JP2007303953A (en) * 2006-05-11 2007-11-22 Fujita Corp Concrete for radiation shielding

Also Published As

Publication number Publication date
CN101302367A (en) 2008-11-12

Similar Documents

Publication Publication Date Title
CN101302367B (en) Anti-neutron size putty
CN105482225B (en) A kind of anti-nuclear radiation rare earth composite material and preparation method thereof
CN104710727B (en) Epoxy resin-matrix neutron and gamma ray shielding composite and preparation method and application
CN107910088A (en) A kind of rare-earth-based flexible core radiation protection material and its preparation method and application
Jumpee et al. Innovative neutron shielding materials composed of natural rubber-styrene butadiene rubber blends, boron oxide and iron (III) oxide
CN104130546A (en) Preparation method for nuclear radiation shielding material
CN107555850A (en) A kind of composite for neutron shielding and its preparation method and application
CN103183928A (en) High-temperature resisting shielding material with neutron shielding effect
CN105038124A (en) Neutron shielding material for spent fuel shipping flask
CN103886926A (en) Radioactive concentrated liquor solidifying formula
CN103937160B (en) The preparation method of a kind of nuclear radiation shield material
CN106747631A (en) One kind inhales ripple porous ground polymers and its preparation method and application
Liao et al. B4C/NRL flexible films for thermal neutron shielding
CN109545415A (en) A kind of radiation protection material
CN105004681A (en) Chemical stability evaluating method of fluorapatite ceramic solidification body
Li et al. Efficient neutron radiation shielding by boron–lithium imidazolate frameworks
CN104591955A (en) Preparation method of radioactive methyl iodide
CN102796291A (en) Neutron and gamma-ray protection latex composite material and preparation method thereof
DE1769563B1 (en) Neutron absorbing material and process for its manufacture
Tajul Ariffin et al. Effect of boron carbide addition on the strength and physical properties of concrete
US3203906A (en) Bituminous shielding composition
CN106833290B (en) Thermal neutron shielding coating and preparation method thereof
Salimi et al. Fabrication and radiocharacterization of boron carbide and tungsten incorporated rubber shields
Li et al. Preparation and shielding performance of gamma ray shielding composite materials based on 3D printing technology
Bhuiyan et al. Studies of neutron shielding properties of ilmenite-magnetite concrete using a 252Cf source

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