[en] Description is given of a joint for connecting radiation-shielding elements end-to-end, characterized in that the joint is located between the adjacent end-portions of parts of reduced thickness of the shielding elements and that it comprises a plurality of filling elements and of weld-elements connecting the latter to the adjacent end-portions of the radiations-shielding elements

[en] It is shown that the fractal dimension of Sierpinski gasket as a conductor is different from that for its geometry. The fractal dimension of Sierpinski gasket can be defined as D = D_Ε + iD_R. D_Ε and D_R are the fractal dimensions determined from its conductance and resistance, respectively. For 2-d Sierpinski gasket D_R = 3.8 and D_Ε = 1/D_R = 0.263, while for 3-d Sierpinski tetrahedron D_R = 2.41 and D_Ε = 0.415. (author). 4 refs, 5 figs

[en] Gasket-holder comprising 2 arms with tongues holding the gasket and fixing devices on a pipe clamp fitting and centering means. Application is made to fit circular gaskets on pipe with conic end in adverse environment

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No abstract available

[en] BAM proposes to introduce a data sheet which contains appropriate identification testings to ensure the compliance of the gaskets to be installed into the packaging with the ones of the approved design. This data sheet refers to national and international test standards in order to be also used in other countries

[en] The 9975 shipping package is used within the DOE complex for shipping special nuclear materials. The shipping packages are currently approved for up to 20 years storage in K-Area Complex (KAC) and work continues to provide technical basis to extend that period. Several techniques have been used at Savannah River National Laboratory to monitor the aging performance of Viton ® GLT or GLT-S fluoroelastomer O-rings. These experiments all involve accelerated aging of the O-ring samples at elevated temperatures. This report describes efforts to extend the service life estimate of GLT and GLT-S O-rings used in the 9975 shipping package.

[en] A nuclear reactor containment arrangement is described incorporating a permanent cavity to vessel seal in the form of a flexible quarter-circular annular steel gasket affixed to and extending between the reactor vessel seal plate and cavity wall. The seal functions to isolate the periphery of the vessel from a permanent water-tight compartment above the reactor vessel which is flooded during refueling operations to minimize the release of radiation upon exposure of the nuclear core. The seal is designed to accommodate both radial and axial expansion of the pressure vessel relative to the cavity wall occurring during reactor operation without breaking the water-tight integrity of the seal. The pressure vessel ventilation system is provided with an air exit duct at the reactor nozzle level to facilitate the circulation of air around the periphery of the vessel which would otherwise be restricted at the seal to vessel interface. (author)

[en] The application concerns a seal with a U-shaped sealing element. The sealing element consists of a stiff, elastic endless track, similar to a hose halved in the axial direction; the cross-section can change between ovoid and a flat segment of a circle and is free of bends. A counterbearing situated in the centre of its convex surface is used to spread the sealing element apart, i.e. it is a counterbearing rail parallel to the sealing element and a tensioning screw, which produces tension between the spreading rail and counterbearing rail. The seals according to the invention have proved successful in nuclear reactor construction. (RB)