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AbstractAbstract
[en] In this work, lead glass doped with 50%, 55%,60%, 65%, and 70% w/w Pb3O4. After that, glass mixtures were melt at 1,250οC with 4 hours soaking time. Molten glass was shaped by mould casting technique then annealed at 700οC and cooled down to room temperature. It was found that the glass with 60%w/w Pb3O4 show maximum absorption coefficient of about 0.383 cm-1 with I-131 at energy 364 keV. The observed refractive indices of the samples range between 1.5908 to 1.5922
Primary Subject
Source
Jun 2003; 7 p; 9. Nuclear Science and Technology Conference; Bangkok (Thailand); 19-21 Jun 2003; Also available from Office of Atomic Energy for Peace, BK(TH)
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Miscellaneous
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Conference
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AbstractAbstract
[en] The invention relates to compositions, methods of production, and uses of non-combustible nuclear radiation shields, with particular emphasis on those containing a high concentration of hydrogen atoms, especially effective for moderating neutron energy by elastic scatter, dispersed as a discontinuous phase in a continuous phase of a fire resistant matrix
Original Title
Patent
Primary Subject
Source
31 Oct 1978; 20 p; US PATENT DOCUMENT 4,123,392/A/
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Patent
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AbstractAbstract
[en] A portable shielding basket used for personnel protection from ionizing radiation in inspections, repairs and maintenance consists of an outer wall consisting, in turn, of an outer and inner jackets with a sealing fill in between them, and of a bottom consisting of a base and a floor plates. A support platform is provided between the top edges of the outer and inner jackets of the outer wall. It is fenced with a hollow elastic sealing border. The basket bottom is divided into a peripheral fixed part and an inner loose part. A gap is provided between the base plate and the circular peripheral basket base. The basket is designed for use in inspection, cleaning and repairs of the top sealing surface of the main circulating pump body and of its suction branch. (J.B.). 1 fig
Original Title
Prenosny tieniaci kos
Primary Subject
Source
15 May 1989; 17 Mar 1987; 4 p; CS PATENT DOCUMENT 261819/B1/; CS PATENT APPLICATION PV 1789-87.G; Application date: 17 Mar 1987
Record Type
Patent
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Tugrul, B.; Yavuz, M.A.; Okka, M.
Istanbul Technical Univ. (Turkey). Inst. for Nuclear Energy1986
Istanbul Technical Univ. (Turkey). Inst. for Nuclear Energy1986
AbstractAbstract
[en] Small volumes with lead brick and lead glass shielding are used, and in nuclear technology we call them ''hot cell''. Furthermore for separating the exposure rooms from the operator rooms lead glassed windows of heavy concreate walls can be used. Unfortunately, these glasses can not be produced in Turkey. ordinary crystals which have lead-oxide in them, can be produced in Turkey, in this essay we have investigated the usage of ordinary crystals for the radiation shielding. Crystals have been tested with different types of radiation and ''radiation absorbtion'' curves, ''half thickness'' and ''tenth value thickness'' have been calculated. (author)
Original Title
Radyasyon zirhlamasi amaciyla kristal camlarin kullanimi
Primary Subject
Source
1986; 5 p; Industrial cooperation in the field of nuclear technology; Istanbul (Turkey); 15-17 Oct 1986
Record Type
Miscellaneous
Literature Type
Conference
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INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
This record replaces 06196960
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Journal Article
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AbstractAbstract
[en] The radiation shielding properties of different types of building materials were investigated against gamma-radiation
Primary Subject
Source
6. international conference of the Balkan Physical Union; Istanbul (Turkey); 22-26 Aug 2006; (c) 2007 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Literature Type
Conference
Journal
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
External URLExternal URL
Salinas, Isabel Cristina Poquet
Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia (COPPE)2006
Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia (COPPE)2006
AbstractAbstract
[en] This study presents a methodology for the determination of the air kerma inside buildings due to contamination on the external surfaces and the shielding factors for the construction material to be used on emergency assessment systems for urban areas. The commonly used construction materials were simulated with the MCNP computer code. A special methodology to simulate the bricks with holes were developed, mixing all different regions into a single one, making the simulation easier and faster. The effective density and the attenuation coefficients for the 50-3000 keV energy range were determined. The effective protection for the bricks with no cement cover decreases by 40-50% for energies greater then 300 keV when compared to bricks covered on both sides. With the data made available it was possible to evaluate the influence of the construction materials densities and thickness on the exposure due to external surfaces contamination and to estimate the error on the dose when the shielding factor applied on the calculation differs from the more realistic ones. The shielding factors for three types of walls were determined for a five rooms house. Special protection procedures should be applied for houses built with bricks with no cement cover, because they are due to the double of the dose when compared to houses built with bricks two-sided cement covered. The influence of windows and doors were evaluated too. This work was developed at the IRD in order to provide information on the construction material commonly uses on building in Brazil. (author)
Original Title
Determinacao dos fatores de blindagem para construcoes tipicamente brasileiras
Primary Subject
Source
Oct 2006; 136 p; 76 refs., 19 figs., 27 tabs.; Tese (Ph.D.)
Record Type
Miscellaneous
Literature Type
Thesis/Dissertation
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LanguageLanguage
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Sugiyama, Akimasa; Taniguchi, Hitokazu; Ogura, Kazuyuki.
Dainichi-Nippon Cables Ltd., Osaka1984
Dainichi-Nippon Cables Ltd., Osaka1984
AbstractAbstract
[en] Purpose: To provide a radiation shielding putty-like composition excellent in radiation shielding performance and shape-retainability after its application and being capable of removing with ease after the application. Constitution: The binder for use in the composition includes liquid or semi-solid grease, liquid or semi-solid organic or inorganic polymers or the mixture thereof having a viscosity at 250C of more than 105 CST and non-mixing consistensity of more than 150. The composition comprises 500 - 4000 parts by weight of inorganic powder per 100 parts by weight of the binder. The inorganic powder usable herein functions as radiation shielding material and includes lead, zinc, copper or oxides and compounds thereof having a density of more than 5. The radiation shielding putty composition has a softness ranging from 1 - 25 (1 mm) at ambient temperature and a density of more than 4. Further, from 0.1 to 50 parts by weight of asbestos or like other fibers are kneaded per 100 parts by weight of the binder using a roll or the like in order to retain the configuration. (Seki, T.)
Primary Subject
Source
26 Nov 1984; 12 May 1983; 5 p; JP PATENT DOCUMENT 59-208500/A/; JP PATENT APPLICATION 58-82972; Available from JAPIO. Also available from INPADOC; Application date: 12 May 1983
Record Type
Patent
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INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The standard presents the types, specifications and marking of lead blocks. The general technical requirements and types are given as are the extent of and procedures for testing the observance of the standard. Packing, storage, and guarantees given by the producer are described. (E.S.)
Original Title
Vyrobky radiacne ochranne techniky. Olovene bloky
Primary Subject
Source
1981; 8 p; Vydavatelstvi UNM; Prague (Czechoslovakia); CSN--403801; Czechoslovak State Standard based on CMEA Standard ST SEV 235-75.
Record Type
Book
Literature Type
Standard
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] In spite of the fact that Basalt is a widespread type of rock, there is very little available information on using it as aggregates for concrete radiation shielding. This paper investigates the possibility of using Basalt for the aforementioned purpose. The results have shown that Basalt could be used successfully for preparing radiation shielding concrete, but some attention should be paid to the choice of the suitable types of Basalt and for the neutron activation problem that could arise in the concrete shield. (authors)
Primary Subject
Secondary Subject
Source
Available from doi: http://dx.doi.org/10.1093/rpd/ncs163; Country of input: France; 8 refs
Record Type
Journal Article
Journal
Radiation Protection Dosimetry; ISSN 0144-8420;
; v. 154(1); p. 127-131

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