No abstract available

[en] In the fuel rod clusters of nuclear reactors the flow pressure of the coolant may cause a displacement of the geometrical position of single fuel rods. Now a spacer is proposed fixing at least the four corner fuel rods within the annular flow channel of a nuclear reactor. This spacer has a supporting part comprising four lateral ties connected by four corner ties, thus forming a uniform rigid structure. At the end of each lateral tie an L-shaped fin is mounted which on the one hand serves to fix the corner fuel rods and on the other to guide the coolant flow. (UWI)

[en] This invention concerns the creation of a reactor vessel support that does away at low cost with the fitting of seals. This support includes a vessel closure system structure, the vessel being fitted with a peripheral flange, to be maintained by the wall of a container, surrounding the vessel radially, as well as a support ring fitted to the flange and supported by the edge of the container. The support ring and the plug structure are directly connected to the upper surface of the vessel flange

No abstract available

[en] A supporting system is proposed for vapor generators of the 'supported' type. Said supporting system is intended to compensate the disparities of thermal expansion due to the differences in the vertical dimensions of the tubes in the walls of the combustion chamber and their collectors compared to that of the balloon tanks and the connecting tube clusters of vaporization, the first one being longer than the second ones. Said system makes it possible to build said combustion chamber higher than the balloon tanks and the tube clusters of vaporization. The capacity of steam production is thus enhanced

[en] This invention essentially concerns a trunnion support acting as a bearing intended, in particular, for supporting a nuclear reactor vessel in a metal structure

[en] This invention relates to a supporting rack for nuclear fuel rods. It particularly concerns facilities for laterally supporting a storage rack of nuclear fuel under water. This nuclear fuel rack is placed in a containment with virtually vertical walls. It includes a certain number of cells each of which is dimensionally designed to take one fuel rod and is so placed that one side is practically parallel with one of the walls in question and at a certain distance from it. It also includes a structure for counteracting seismic movements

[en] The current EN 1992 provides structured information related to the design of reinforced concrete columns or reinforced concrete column beam connections. On the other hand, EN 1994 gives enough information on the design of composite columns but none of the current codes provide details about a possible transfer zone in the case of usage of RC and composite column solution. The current study tends to fill the gap between these two norms. In the current experimental campaign, carried out in the frame of the European research program SmartCoCo, it is presented as a calibration method for a tentative design method which has been elaborated by one of the authors based on theoretical strut and tie reasoning. The objective of the current paper is to present the results of the experiments and aims to validate the theoretical approach for calculating the force transfer mechanism in the transfer zone. The experimental campaign comprises of 4 columns and 4 column-beam connections, all of them being composed by a RC part and a composite. The tests are performed on vertical column, simply supported with a width of 350mm, length of 380 mm and a height of 3850 mm with a regular concrete quality (C25/30). This contribution describes the test specimens, summarizes their design, presents a selection of the most relevant results from analog and digital measurements and a short interpretation of the obtain results. We concluded from this set of tests that the new design method is able to explain the force transfer mechanism with a good accuracy and can therefore be considered as a suitable solution for designing practical cases. (Author)

[en] According to the present invention there is provided an improved arrangement for supporting a reactor vessel within a containment structure against static and dynamic vertical loadings capable of being imposed as a result of a serious accident as well as during periods of normal plant operation. The support arrangement of the invention is, at the same time, capable of accommodating radial displacements that normally occur between the reactor vessel and the containment structure due to operational transients. The arrangement comprises a plurality of vertical columns connected between the reactor vessel and a support base within the containment structure. The columns are designed to accommodate relative displacements between the vessel and the containment structure by flexing. This eliminates the need for relative sliding movements and thus enables the columns to be securely fixed to the vessel. This elimination of a provision for relative sliding movements avoids the spaces or gaps between the retention members and the retained elements as occurred in prior art arrangements and, concomitantly, the danger of establishing impact forces on the retention members in the event of an accident is reduced. (author)

[en] Supporting rings for the support of a pressure vessel designed for a nuclear reactor can be fitted without interrupting concreting jobs. U-shaped recesses are provided in the biological shield designed for the supporting ring. The supporting ring consists of partial segments which are connected at their contact points by means of threaded joints and form a stable unit. It is advantageous to fill up the cavities between the supporting ring and the recesses with compressible material. (UWI)