Abstract:
A very long term storage installation for calorific products such as nuclear waste, comprising at least one closed cavity (10) receiving at least one container (14) for the containment of said products. In order to evacuate the heat emitted by the products thus stored, a jacket (26) is placed around each container (14), whereby a thermosiphon (24) is associated with said jacket and the cold source thereof consists of an air-cooled refrigerant condenser arranged above a slab (20) which closes the cavity towards the top. The container(14) is enclosed by the preferably interchangeable jacket (26) in a tight manner.
Abstract:
The invention concerns a method and a device for separating a neutron absorber (A) from a cooling medium (K) in a nuclear facility. According to the inventive method, the cooling medium (K) is evaporated by heating, the evacuated cooling medium vapor (KD) is compressed in a compressor (51) by raising the temperature and utilized for evaporating other cooling media. Preferably, a fraction of the compressed cooling medium vapor (KD) is fed to a condenser (74). Preferably, a cleaning gas device (100) and a blocking fluid device (121) are available.
Abstract:
The invention concerns a method and a device for separating a neutron absorber (A) from a cooling medium (K) in a nuclear facility. According to the inventive method, the cooling medium (K) is evaporated by heating, the evacuated cooling medium vapor (KD) is compressed in a compressor (51) by raising the temperature and utilized for evaporating other cooling media. Preferably, a fraction of the compressed cooling medium vapor (KD) is fed to a condenser (74). Preferably, a cleaning gas device (100) and a blocking fluid device (121) are available.
Abstract:
The present invention essentially involves using a solidification material (15) for filling the empty cavities (7, 9) in premises which have been evacuated pursuant to an accident that occurred during the exploitation of a given object. If need be, specific ingredients consisting of neutron absorbers as well as superplasticisers can also be added to this material. The filling process is carried out according to a stratification technique starting from the bottom towards the top and from the periphery towards the centre of the structure, wherein the layer thus deposited is given time to rest in order to form a single monolithic block. The height of the monolithic block thus formed depends on the amount and the distribution of the nuclear fuel, on the time necessary for the block to rest until the filling is completed, on the conditions of the building structures as well as on the filling material itself. The height of the block is further determined for each practical case. Using specially selected and formed materials, it is thus possible to provide a reliable protection structure against radioactive and harmful nuclear substances while using industrial facilities and materials already available on the market.
Abstract:
The invention relates to a device for the catalytic conversion of hydrogen. The device is used for eliminating hydrogen which has been produced as a result of an incident. Said hydrogen is eliminated effectively and without producing a backfire. The aim of the invention is to improve the effect of the recombiner and to prevent the containment atmosphere from heating up. To this end, a recombiner (8) with a plurality of catalytically effective catalyst elements (8a) is arranged in the containment containing the gas mixture, a cooling device (10) is placed downstream from the recombiner (8) and a further cooling device (4) is placed upstream of the recombiner (8).
Abstract:
The invention relates to the use of amorphous, nickel based alloys as materials for absorption sheaths for reactor fuel elements. Said amorphous nickel based alloys contain 20-35 % boron atoms, so that the boron content in comparison with known crystalline austenitic boron steels can be increased by a factor of 2-4.
Abstract:
The invention concerns a grid in the insert of which are arranged, at regular intervals, assembling notches with transverse inserts and, between at least some pairs of notches, a spring (22, 30) for maintaining the pencil comprising two elastic strips (24) cut out in the insert planar wall and forming a single piece therewith. Each strip extends transversely to the insert and is connected to the part of the insert containing the pencil by its two ends. The strips project freely towards the inside of the cell concerned and are connected in their middle by a transverse connecting strap (26), projecting relative to the two strips.
Abstract:
The invention relates to an ignition system (1) with a number of spark igniters (4) for recombining hydrogen in a gas mixture. The aim of the invention is to provide an ignition system of this type which guarantees reliable, early ignition of an ignitable gas mixture by means of preionisation of the mixture, even with comparatively rapid gas displacement processes. To this end, each spark igniter (4) is configured as a rapid-pulse igniter with an operating frequency of approximately more than 10 Hz. The spark igniters (4) are interconnected in groups for supplying energy in order to ensure reliable ignition of an ignitable gas mixture in the event of a momentary breakdown of external devices as well as in the event that the ignition system is required to run for a particularly long time. Each group of spark igniters (4) is connected to a joint intermediate energy store (8), said intermediate energy stores being connected to a central energy supply unit (7).
Abstract:
In order to measure the deformation of a guide tube of a nuclear fuel assembly (14), an eddy current sensor (38) is horizontally displaced so as to make it pass successively on a vertical rectilinear metal mark (42), and on the guide tubes of a first row of the assembly (14) maintained in vertical position; the output signal of the sensor is measured and the positions of the sensor (38) corresponding to the extrema of the signal with respect to said mark are memorised; this step is repeated at several heights on the row, then on the other rows. The same steps are repeated displacing the sensor (38) in a direction orthogonal to the first. From the memorised positions, the amplitude and the direction of the positional deviations with respect to the nominal position for a rectilinear tube, at each of these heights are computed.
Abstract:
A fuel element assembly has a non-symmetrical (in plan) distribution of fuel material and is composed of nuclides of differing concentrations in the nuclear fuel of the fuel elements which are disposed in such a way as to form two subsidiary zones about the plane through the central longitudinal axis of the assembly containing different nuclide concentrations (averaged by volume of nuclear fuel). The active zone of the nuclear reactor contains at least some of these "non-symmetrical" assemblies in which the subsidiary zones whose nuclear fuel contains a lower concentration of fissile nuclides are aligned along the central longitudinal axis of the active zone, whilst the fuel elements of the peripheral series adjoining the side reflector can have an orientation opposite to that of the subsidiary zone with the lower concentration of fissile nuclides. In addition, at least some of the differing types of fuel elements forming the "non-symmetrical" fuel elements can be made with a nuclear fuel containing a depleted absorber.