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Bosquet, M.
EUROMAS, 84 - Bollene (France)
EUROMAS, 84 - Bollene (France)
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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AbstractAbstract
[en] The disclosure pertains to a clamping apparatus having a stud capturing portion and a stud facing portion bolted together so as to compressively support a radiation-proof sheet material, such as lead sheeting, there-in-between. The interior wall covering material, such as panelling or wall board, is secured to the external surface of the stud facing portion. No nails are required to support the radiation-proof sheeting material, thereby minimizing accidental leakage due to harmful radiation passing through openings inadvertently disposed in the radiation-proof sheeting in the conventional nail securing supporting thereof. A pair of radiation-proof tracks capture the free ends of the stud capturing portion and the stud facing portion
Original Title
Patent
Primary Subject
Source
26 Jul 1977; 4 p; US PATENT DOCUMENT 4,038,553/A/
Record Type
Patent
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INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Le role du plomb dans la conception et la realisation des protections en milieu nucleaire
Primary Subject
Record Type
Journal Article
Journal
Materiaux et Techniques; (no.11); p. 481-486
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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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Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Safety apparatus for use in administering radioactive serums by a syringe, without endangering the health and safety of the medical operators is described. The apparatus consists of a sheath and a shield which can be retracted into the sheath to assay the radioactive serum in an assay well. The shield can be moved from the retracted position into an extended position when the serum is to be injected into the patient. To protect the operator, the shield can be constructed of tantalum or any like high density substance to attenuate the radiation, emanating from the radioactive serums contained in the syringe, from passing to the atmosphere. A lead glass window is provided so that the operator can determine the exact quantity of the radioactive serum which is contained in the syringe
Original Title
Patent
Primary Subject
Secondary Subject
Source
10 Aug 1976; 6 p; US PATENT DOCUMENT 3,973,554
Record Type
Patent
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Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Hirscheider, E.; Balk, O.
Gesellschaft fuer Strahlen- und Umweltforschung m.b.H., Muenchen (Germany, F.R.); Deutsches Patentamt, Muenchen (Germany, F.R.)
Gesellschaft fuer Strahlen- und Umweltforschung m.b.H., Muenchen (Germany, F.R.); Deutsches Patentamt, Muenchen (Germany, F.R.)
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
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
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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 - 2016
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 - 2016
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
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Alonso, J.V.S.; Torio, P.P.
Proceedings of the 4. International congress of the International Radiation Protection Association. Paris, 24-30 April 1977
Proceedings of the 4. International congress of the International Radiation Protection Association. Paris, 24-30 April 1977
AbstractAbstract
[en] The control of ocular protection medium which is normally used by workers, finds itself confronted by unsurmountable difficulties. Transmission determination needs fine glass lenses, extrapolating the values obtained to the real value of the medium used. The degree of protection required of the glass used by workers has been determined using successive approximations. The work method is quick and simple, and the apparatus used is within the reach of any medium sized laboratory. A theoretical justification has been made of the fundamental principles of the method; for example, the protective power of various filter lenses used by workers in this country has been determined. The method has been centred on the possibility of its practical application. The results obtained are interpreted taking into consideration a possible emissing source, and their discussion is based on prevailing standards which exist in most European countries. The control carried out has allowed to state that in most cases the protection medium used is not adequate, owing to a poor selection or an inadequate maintenance
Primary Subject
Source
Anon; v. 2 p. 385-388; 1977; v. 2 p. 385-388; Association Internationale de Protection contre les Rayonnements; Fontenay-aux-Roses, France; 4. International congress of the International Radiation Protection Association: radiation protection as an example of action against modern hazards; Paris, France; 24 - 30 Apr 1977; Copies available: M. Gilbert Bresson, General Secretary IRPA, B.P. no.33, 92260 Fontenay-aux-Roses (France)
Record Type
Book
Literature Type
Conference
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Bowden, A.V.
Southern Metal Works, Inc., Columbia, SC (United States)
Southern Metal Works, Inc., Columbia, SC (United States)
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
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AbstractAbstract
[en] Cerrobend alloy casts are made to define the desired electron field shapes. These custom casts are fabricated for the selected electron applicator size that has been chosen for the patient. When the cast is placed into that selected electron applicator, it will block out areas that are not to be treated. When an all metal mold assembly was used for the fabrication of these casts, the lip region of the cast which is used to accurately align the cast in the actual treatment applicator, had an irregular edge that prevented an accurate alignment of the cast. To eliminate the irregular edges on the lip region of the cast, the metal mold assembly was heated to approximately 80-85 degrees C before the molten cerrobend alloy was poured into it. The heating of the metal mold assembly helps eliminate the irregular edges on the lip region of the cast. Unfortunately it also created new flaws such as holes, dents, cracks and/or crystallization of the cast as it solidified. These flaws were controlled by cooling the metal mold assembly and the cast immediately after the pouring of the molten cerrobend alloy, evenly with water
Primary Subject
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Journal Article
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