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Bowden, A.V.
Southern Metal Works, Inc., Columbia, SC (United States)1993
Southern Metal Works, Inc., Columbia, SC (United States)1993
AbstractAbstract
[en] A construction module is described for use in protecting personnel against emissions from radioactive material comprising: a shaped member suitable for assembly with other shaped members to form a structure for shielding personnel; said shaped members being formed from suitable shielding material capable of excluding passage of emissions from radioactive material and having adjoining surfaces for reception closely adjacent complementary surfaces of other shaped members; and a synthetic polymeric material having been formed by molding to engage and extend over an exterior surface of said shaped member forming a hardened coating layer protecting the shielding material from contamination by exposure to radioactive material and serving as a readily decontaminated surface to avoid exposure of personnel to emissions from radioactive material; whereby an encapsulated construction module is formed suitable for assembly as a structure to shield personnel and which is easily decontaminated avoiding exposure to emissions from radioactive material
Primary Subject
Source
6 Jul 1993; 11 Feb 1992; [10 p.]; US PATENT DOCUMENT 5,225,685/A/; US PATENT APPLICATION 7-833,886; Available from Patent and Trademark Office, Box 9, Washington, DC 20232 (United States); Application date: 11 Feb 1992
Record Type
Patent
Country of publication
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Bosquet, M.
EUROMAS, 84 - Bollene (France)1992
EUROMAS, 84 - Bollene (France)1992
AbstractAbstract
[en] The shield is composed of a double-walled hollow body, for instance in composite materials, enclosing a part of a circuit (vane, pipe, etc.), the inside cavity between the walls can be filled (or evacuated) with a filling material such as hematite pig iron balls
Original Title
Dispositif et installation pour la protection biologique d'element de circuit de fluide radioactif
Primary Subject
Source
23 Oct 1992; 18 Apr 1991; 14 p; FR PATENT DOCUMENT 2675619/A/; FR PATENT APPLICATION 9105020; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 18 Apr 1991
Record Type
Patent
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INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to shielding enclosures: their application and procedures guides
Primary Subject
Secondary Subject
Source
Practical radiation safety manual; Mar 1996; 50 p
Record Type
Report
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AbstractAbstract
[en] A radiological screen for placing on a patient's skin is discussed, comprising a flat jacket containing a fine particulate filler and a settable resin binder, the fine particulate filler being of a material which absorbs medical radiation, and the jacket including a window to transmit such radiation through the flat jacket. 16 claims, 4 drawing figures
Primary Subject
Source
2 Mar 1976; 6 p; US PATENT DOCUMENT 3,942,023/A/
Record Type
Patent
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Warner, P.
EPJ Web of Conferences, Proceedings of the 13. international conference on radiation shielding and 19. topical meeting of the radiation protection and shielding division of the American Nuclear Society - 20162017
EPJ Web of Conferences, Proceedings of the 13. international conference on radiation shielding and 19. topical meeting of the radiation protection and shielding division of the American Nuclear Society - 20162017
AbstractAbstract
[en] For any appreciable radiation source, such as a nuclear reactor core or radiation physics accelerator, there will be the safety requirement to shield operators from the effects of the radiation from the source. Both the size and weight of the shield need to be minimised to reduce costs (and to increase the space available for the maintenance envelope on a plant). This needs to be balanced against legal radiation dose safety limits and the requirement to reduce the dose to operators As Low As Reasonably Practicable (ALARP). This paper describes a method that can be used, early in a shield design, to scope the design and provide a practical estimation of the size of the shield by optimising the shield internals. In particular, a theoretical model representative of a small reactor is used to demonstrate that the primary shielding radius, thickness of the primary shielding inner wall and the thicknesses of two steel inner walls, can be set using the Lagrange multiplier method with a constraint on the total flux on the outside of the shielding. The results from the optimisation are presented and an RZ finite element transport theory calculation is used to demonstrate that, using the optimised geometry, the constraint is achieved. (author)
Primary Subject
Secondary Subject
Source
Malgavi, F.; Malouch, F.; Diop, C.M'B.; Miss, J.; Trama, J.C. (eds.); EDP Sciences, 17, Avenue du Hoggar, Parc d'Activite de Courtaboeuf, BP 112, F-91944 Les Ulis Cedex A (France); v. 153 [1590 p.]; 2017; p. 06012.p.1-06012.p.6; ICRS-13: 13. international conference on radiation shielding; Paris (France); 3-6 Oct 2016; RPSD-2016: 19. topical meeting of the radiation protection and shielding division of the American Nuclear Society; Paris (France); 3-6 Oct 2016; Available from doi: http://dx.doi.org/10.1051/epjconf/201715306012; 1 ref.; This record replaces 51039547
Record Type
Book
Literature Type
Conference
Country of publication
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Related RecordRelated Record
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Hirscheider, E.; Balk, O.
Gesellschaft fuer Strahlen- und Umweltforschung m.b.H., Muenchen (Germany, F.R.); Deutsches Patentamt, Muenchen (Germany, F.R.)1978
Gesellschaft fuer Strahlen- und Umweltforschung m.b.H., Muenchen (Germany, F.R.); Deutsches Patentamt, Muenchen (Germany, F.R.)1978
AbstractAbstract
[en] With the shaped brick from metal or concrete radiation protection walls can be erected in dry construction a single shape for the bricks being sufficient. The connection contours of the shaping bricks are derived from the generated surface of an equilateral prisma. If one end is shaped concave and the other convex it becomes possible to reproduce straight lines, angles, polygons, and circles and to fully cover surfaces. In order to balance wall alternations at the connection contours reinforcement ribs are arranged at the concave brick ends. (ORU)
[de]
Mit dem Formbaustein aus Metall oder Beton koennen Strahlenschutzwaende in Trockenbauweise erstellt werden, wobei eine einzige Steinform ausreicht. Die Anschlusskonturen der Formbausteine werden aus der Mantelflaeche eines gleichseitigen Prismas abgeleitet. Wird ein Ende konkav und das andere konvex ausgebildet, so ist es moeglich, Geraden, Winkel, Vielecke und Kreise nachzubilden und Flaechen voll auszulegen. Um die Wandschwaechung an den Anschlusskonturen auszugleichen, sind an den konkaven Steinenden Verstaerkungsrippen angeordnet. (ORU)Original Title
Formbaustein
Primary Subject
Source
6 Jul 1978; 11 p; DE PATENT DOCUMENT 2700088/A/
Record Type
Patent
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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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Ennis, M. G.; Tobin, T. J.; Cha, Y. S.; Hull, J. R.
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)2000
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)2000
AbstractAbstract
[en] Tests were conducted to determine the electrical and magnetic characteristics of a superconductor shielded core reactor (SSCR). The results show that a closed-core SSCR is predominantly a resistive device and an open-core SSCR is a hybrid resistive/inductive device. The open-core SSCR appears to dissipate less than the closed-core SSCR. However, the impedance of the open-core SSCR is less than that of the closed-core SSCR. Magnetic and thermal diffusion are believed to be the mechanism that facilitates the penetration of the superconductor tube under fault conditions
Primary Subject
Source
30 Jun 2000; 6 p; Applied Superconductivity Conference 2000; Virginia Beach, VA (United States); 17-22 Sep 2000; W-31109-ENG-38; Also available from OSTI as DE00759062; PURL: https://www.osti.gov/servlets/purl/759062-3e5YVy/webviewable/
Record Type
Report
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Conference
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AbstractAbstract
[en] The Light Ion Fusion Target Development Facility (TDF) is expected to test approximately ten targets per day having yields in the 50 to 800 MJ range. This large number of high yield microexplosions creates design problems in the TDF that are not present in PBFA-I and PBFA-II. The TDF would be the first light ion facility where radioactivity in the target debris and induced in the facility itself constitute a biological hazard. It must have a first wall and a target diagnostics package that can survive repeated mechanical and thermal pulses from the target microexplosions. In addition, the repetition rate is much higher than for present day light ion beam drivers. A preliminary conceptual design for the TDF including a reaction chamber, biological shield, target diagnostics package and driver that addresses these and other problems is presented
Primary Subject
Secondary Subject
Source
6. topical meeting on the technology of fusion energy; San Francisco, CA (USA); 3-7 Mar 1985; CONF-850310--
Record Type
Journal Article
Literature Type
Conference
Journal
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Benoit, J.
Centre National d'Etudes Spatiales, 31 - Toulouse (France)1985
Centre National d'Etudes Spatiales, 31 - Toulouse (France)1985
AbstractAbstract
[en] In this process a neutron absorber is introduced in one, at least, of the component of the composite materials, the absorber used is gadolinium for protection against neutrons of personnal or electronic devices
[fr]
Le procede de fabrication consiste a introduire un materiau neutrophage dans au moins un des composants du materiau composite: le materiau neutrophage est du gadolinium pour la protection du personnel ou des dispositifs electroniquesOriginal Title
Procede de fabrication de structures en materiaux composites formant blindage neutronique
Primary Subject
Secondary Subject
Source
21 Jun 1985; 14 Dec 1983; 6 p; FR PATENT DOCUMENT 2556876/A/; FR PATENT APPLICATION 8320005; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 14 Dec 1983
Record Type
Patent
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