[en] In conventional doors which are employed for chambers or vessels requiring airtightness and watertightness such as the airtight compartment of a reactor container or laboratory for handling radioactive materials, the angle of revolution of an operating wheel for driving a locking piece engaged with the door and the distance of movement of the locking piece hold a fixed proportional relation during the period of closing the door. Therefore, an operating force necessary for operating the wheel increases since the elastic force of a packing gradually increases with the tightening of the door. For this reason, it is difficult to sufficiently secure the door to an opening and to thus hold the chamber or vessel perfectly airtight and watertight. According to this invention, the locking piece can move in the direction in which the door closes, and a transmission mechanism is interposed between the locking piece and the operating wheel. Owing to the transmission mechanism, when the door is closed, the locking piece is engaged with the door and then moved in the closing door direction by the revolution of the operating wheel, and herein, the rate of the amount of movement of the locking piece in the closing door direction relative to the revolution of the operating wheel over a certain angle is gradually decreased with the increase of the angle of revolution of the operating wheel in the closing door direction. Thus, the door can be closed perfectly airtight and watertight without requiring any large operating force. (S. Takasuka)

[en] A device is described for locking the two closures of a container and an enclosure, to allow transport or transfer of radioactive materials without contamination

[en] The rule applies to the fabrication of safety containments of steel for stationary lightwater reactors including the supports connected with the safety containment, as well as for pressure-bearing parts of transfer canals. (orig./HP)

No abstract available

[en] A shipping container containing a transfer vessel is contacted with the contaminated enclosure. The three coupled doors of the enclosure, of the container and of the vessel are removed together and products are transferred from the enclosure to the vessel, without communication of the atmosphere of the container outside the vessel and of the enclosure are in communication. The 3 doors are closed and the container is removed for transport toward a second enclosure. The three doors of this second enclosure and of the container are opened to introduce in the second enclosure the transfer vessel containing the products

[en] The invention concerns a safety device for a locking system between two vessels closed by doors. The locking system includes a ring for locking the first vessel on to the second vessel and an operating lever for locking the double door. The safety device is composed of two locks controlled electrically by microswitches and for preventing vessel from being dismantled after unlocking, or the opening of the double door or for preventing door from opening when vessel is removed. Applies to biological and nuclear handling in a sealed vessel

[en] A material access lock as defined by this standard is a pressure-resistant and technically gas-tight hollow body connected with the containment and which has got two gates, the inner one of which connects the lock chamber with the interior of the containment and the outer one of which connects the lock chamber with the exterior. It serves exclusively for transferring material or objects. (orig.)

No abstract available

[en] This paper points out some important shifts in the basic expectations in the performance requirements for containment structures and discusses the areas where the containment structure design requirements and acceptance criteria can be integrated with ultimate test based insights. Although there has not been any new reactor construction in the United States for over thirty years, several designs of evolutionary and advanced reactors have already been certified. Performance requirements for containment structures under design basis and severe accident conditions and explicit consideration of seismic margins have been used in the design certification process. In the United States, the containment structure design code is the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NE-Class MC for the steel containment and Section III, Division 2 for reinforced and prestressed concrete reactor vessels and containments. This containment design code was based on the early concept of applying design basis internal pressure and associated load combinations that included the operating basis and safe shutdown earthquake ground motion. These early design criteria served the nuclear industry and the regulatory authorities in maintaining public health and safety. However, these early design criteria do not incorporate the performance criteria related to containment function in an integrated fashion. Research in large scale model testing of containment structures to failure from over pressurization and shake table testing using simulated ground motion, have produced insights related to failure modes and material behavior at failure. The results of this research provide the opportunity to integrate these observations into design and acceptance criteria. This integration process would identify 'gaps' in the present knowledge and future research needs. This knowledge base is important for gleaning risk-informed insights into the design basis and severe accident behavior of containments. The task of revising various areas of the advanced reactor containment design standards is substantial. (authors)

[en] The data collected to date supports the conclusion that the use of internal monitoring devices to detect the water behavior within a waste storage cell provides an opportunity to respond to indications of cell structural distress before the cell has begun to discharge water contaminated by the wastes. A delay after containment structure failure always occurs before discharged water is identified by the environmental monitoring program. The internal monitoring system provides continuous data about local and general internal conditions. The instrumentation can identify local elements of the containment that need more intensive inspection. The instrumentation offers the ability to identify areas within the containment where liquid extraction or cap repair may be desirable. The internal monitoring system can be replaced at the end of its design life, which provides the flexibility to indefinitely extend the intensive monitoring period of a facility. Since the need to extend the monitoring depends on the individual facility's behavior, the flexibility to extend the system life is an important capability. Therefore, the internal monitoring system provides timely, accurate, and reliable information for planning and evaluating the behavior of the containment structure