DD278265A3 - METHOD AND DEVICE FOR DISPOSING RADIOACTIVE BULB FORMED ABSORBER ELEMENTS (CLUSTER) - Google Patents

Abstract

The method and the device according to the invention are suitable for disposing of highly activated buil-shaped absorber elements by producing a transportable and final storage-capable state. The object of the invention is to develop a disposal method with technological advantages, which is functional, envelope and radiation safe with simple devices feasible. The solution according to the invention is achieved with a method and a device which is characterized by an equidistant transfer of the clusters from the fuel cassette to a stationarily positioned transfer container with separation device and position-oriented cluster guide and thereby ensures reliable comminution with simultaneous contamination-free collection of the cluster sections in a container. The assembly, transport and disposal are carried out according to known methods and with proven devices. Fig. 1

Description

Thereafter, a cluster is removed by means of special gripper radiation safe under water from the fuel cartridge and pulled into a shielded Umladecontainer on the water surface. The dismantling of the cluster takes place in a separate shredding unit, which is arranged via a Umladeschacht and on which the Umlade container is placed. The shredding unit consists of a horizontally rotatable ring with radially displaceable shredding tool. For the collection of the cluster sections disposal containers are arranged in the Umladeschächten, which surrender after filling in transport containers and transported to the repository.

The technological concept is characterized by the manipulation of the transhipment container, which is struck by the crane during the axis-equal positioning above the fuel cassettes as well as the collector removal and can thus influence the handling safety. The cluster removal with the rope-guided special gripper under water requires a complex construction in order to reliably secure the remote-controlled gripping, the damage-free removal and transfer. To ensure the radiation protection, the transhipment container dives into the pool water during the cluster takeover, so that a surface contamination occurs. The illustrated loading of the repository container with the cluster sections can lead to equipment contamination.

The principle of the convertible reloading container with integrated lifting and gripping device has already proven itself in practical nuclear power plant operation for similar highly activated components and applications.

In DE-OS 3301814, a method and a device is proposed for the disassembly of individual elongated Kerninstrumentierungssonden by stepwise lowering and separating while sorting the sections in areas of activity.

Object of the invention

The object of the invention is to provide for hochaktivierte unbundled absorber elements (cluster) a low-envelope process for NPP disposal with advantages voriahrenstechnologischen that guarantees the development of simple radiant safety equipment with high reliability compared to the known solutions for the production of a transportable and storable state as well as the total effort minimized.

Explanation of the essence of the invention

The object of the invention is for the disposal of nuclear power plants with bündiförmigen absorber elements (Clus'c), ate arranged axially displaceable in fuel cassettes, a low-envelope process for disposal by producing a transportable and storable state with a high functional and radiation safety create.

According to the invention, the object is achieved in that the water-filled decay, storage or Umladebecken embedded in racks or shaft tubes fuel cartridges including Jer clusters taken with the existing BSK manipulation technology under water, fed to a stationary clamping and lifting device and kept oriented. Above the water surface, a radiation shield is arranged in the cluster transfer area, on the same axis to the tensioned fuel cartridge, the positioning of the transfer container with gripping and lifting device and separation device takes place with respect to the cluster. Thereafter, the fuel cartridge is lifted vertically out of the water and coupled in the radiation-shielded, air-filled space from below positively to the Umladecontainer. The cluster is struck against the gripper and pulled by a fixed in Umlade container guide plate, so that the order state of the cluster fingers is maintained. The fuel cassette is lowered into the starting position under water and stored again. The reload container including separator is implemented with the cluster on a technological container with a container for the collection of cluster sections. By discontinuous lowering of the cluster with the lifting device of the reloading container through the inserted cutting plate for positive retention, the cluster fingers are separated in pairs in the separation plane with the cutting tool in any part lengths. The cluster sections fall into the collecting container, which is pressed against the loading container in such a way that the loading and unloading opening is covered. Uie separation device is disposed in the rotatable cylindrical radiation protection closure snthält a technological channel in which a horizontally displaceable cutting plate and the cutting tool are arranged with drive. When you turn 90 °, the transfer container and the separator are sealed.

The packaging of the container with the radioactive cluster sections is carried out in the same technological container according to known methods, transport and disposal according to the existing central detection system. D> e advantages of the invention are that maintained by the direct coupling of the fuel assembly with the Umladecontainer without additional Umschlagsprozesse the order state of the cluster, which is tuned with the separation process as a closed technological chain. This eliminates the need for complicated additional cluster manipulations and the complicated special gripper devices required for use above water. The process reliability increases and a damage-free cluster envelope can be realized.

The radiation-shielded arrangement of the transfer container above the water level allows a cluster transfer without surface contamination, so that in normal operation, the decontamination of the transfer container is not required. Due to the stationary arrangement of the Umladeplatzes, z. B. on the edge of the pool, accounts for manipulations with the heavy transhipment container on the crane over the storage pool, so that the handling safety is given. The combination of the radiation protection closure of the transfer container with the separation device ensures that the order state of the cluster is defined to the cutting tool and thus maintained regardless of the turnover process. The separation process can be selected as a function of the order state so that individual or multiple cluster fingers are separated at the same time and thus the required effort for the separation of the cluster is kept low. By the, dichto pressing the container to the transfer container and the overlap of the loading / unloading an uncontrolled spread of radioactive material and an external surface contamination of the container is avoided. The packaging

the cluster sections are made by known methods and with proven devices in the technological container, so that the transport and disposal can be done according to the existing requirements of the central detection system.

embodiment

The invention will be explained below using an exemplary embodiment. In the accompanying drawings show:

Fig. 1: Section through the BSK storage pool at BSK '/ Clusterumschlag

Fig. 2: section through the radiation protection closure with separation device with positively coupled fuel cassette Fig.3: section through the radiation protection closure with separation device and collecting container for cluster sections in working position.

FIG. 1 shows an exemplary embodiment of the takeover of a cluster from a fuel cassette in the transfer container with separating device.

In the water-filled storage tank (1), the fuel cassette including cluster (2, 3) with a transfer rod (4) vertically removed from the BSK-bearing shaft (20) and fed under water horizontally the BSK tensioning and lifting device (5).

The fuel cartridge (2, 3) is tensioned in a position-oriented manner in the BSK tensioning and lifting device (5) arranged stationarily on the edge of the storage tank, and the transfer bar (4) is cut off. On the radiation shield (6) above the water surface of the storage tank (1), the transfer container (&) is positioned on the same axis and in a position-oriented manner relative to the fuel cassette (2; 3).

When the radiation protection shutter (13) and laterally extended cluster section plate (11) in the technological channel (17), the fuel cassette (2; 3) with the BSK tensioning and lifting device (5) lifted vertically out of the water and the head of the fuel cartridge in a form-fitting introduced the Umlade container (8).

FIG. 2 shows the radiation protection closure (13) with separation device (10) in the case of a fuel cassette (2; When laterally extended cluster cutting plate (11) in the clothological channel (17), the cluster (3) with the gripping and lifting device (9) in the air-filled space through the Clusterfühiimgsplatte (7) from the fuel cartridge (2) in the transfer container (8) , The order state ~ * it cluster (3) over the entire length is maintained.

FIG. 3 shows the radiation protection closure (13) with separating device (10), technological container (14) and container (15) for the cluster sections (16) in working position.

Concentric with the cluster guide plate (7) via the drive (18) retracted Clusterschnittplatte (11) and close to the Umlade container (8) pressed container (15) for the cluster sections (16), the loading / unloading (22) of the Umladecontainers ( 8), the cluster (3) of the gripping and lifting device (9) of the Umladecontainerers (8) is lowered. The cluster rods (3) are guided in a form-fitting manner in the cluster cutting plate (11), individual or several cluster rods (3) are separated simultaneously from the separating tool (12) and the cluster sections (16) are collected in the container (15).

For the disposal of the non-separable traverse (21) the cluster fingers from the cluster cutting plate (11) are pulled up, the cluster cutting plate (11) from the technological channel (17) laterally with the drive (18) and traverse (21) from the gripper the gripping and lifting device (9) knocked off. By rotation of the cylindrical radiation protection closure (13) by 90 °, the transfer container (8) with separation device (10) is sealed radiant.

Claims (2)

1. A method for disposing of radioactive bündiförmiger absorber elements (cluster), in particular highly activated, by producing a transportable and storable state by taking over the cluster from the fuel cartridge in a radiation shielded Umladecontainer with separator, converting the Umladecontainers on a technological container with container for cluster sections and discontinuous Feeding the clusters, shredding and collecting in containers, characterized in that in a storage tank (1) under water in the BSK storage shaft (20) arranged fuel cassette (2) including clusters (3) with reloading bar (4) and hoist lifted vertically, fed by horizontally moving a stationary BSK clamping and lifting device (5), fixed in a position-oriented manner and the transfer bar (4) is knocked off, that a transfer container 8) with separating (10), gripping and lifting device (9) and cluster guide plate (7 ) on the same axis as d he strained fuel cartridge (2) positioned on a radiation shield (6) above the water surface dss storage tank (1) is turned off, that the orientation oriented fixed fuel cassette (2) with the BSK clamping and lifting device (5) lifted vertically out of the water and the head of the fuel cassette (2) in the air-filled space from below positively inserted into the transfer container (8) held in this position, the cluster (3) to the gripping and lifting device (9) posted by the cluster guide plate (7) in the Pulling Umlade container (8) while maintaining the order state of the cluster over the entire length that the fuel cartridge (2) without cluster (3) with the BSK tensioning and lifting device (5) moves into the starting position under water and with the Radiation protection closure (13) closed Umlade container (8) with separation device (10) on a technological container (14) is implemented, that the container (15) for the cluster sections (16) closes the loading / unloading opening (22) of the transfer container (8) tightly by pressing, the cluster (3) discontinuously lowered into the cluster cutting plate (11), one or more cluster bars separated simultaneously and the cluster sections (16) in the container (15) are collected. 2. Apparatus for disposing of radioactive bündiförmiger absorber elements, characterized in that the fuel cassette (2) including clusters (3) with the BSK clamping and lifting device (5) coaxially and positively to the radiant over the water surface of the storage tank (1) positioned Umladecontainer (8) with gripping and lifting device (9) is coupled, that at the laterally from the technological channel (17) of the radiation protection closure (13) extended cluster interface plate (11) by the cluster guide plate (7) drawn cluster (3) is positionally determined, the Cluster cutting plate (11) via the drive (18) in the technological channel (17) congruent to the cluster guide plate (7) is arranged and the cluster (3) with the gripping and lifting device (9) the cutting tool (12) under the cluster cutting plate (11) is assigned, that the collecting container (15) covers the loading / unloading opening (22) of the transfer container (8) and seals and after D Rotation of the radiation protection closure (13) by 90 ° with the drive (19) of the transfer container (8) with separation device (10) is sealed radiant. For this 2 pages drawings Field of application of the invention The invention relates to a method and a device for disposal by producing a transportable and storable state of radioactive composite absorber elements (cluster), d'e incurred in the operation of nuclear reactors as highly activated waste. Characteristic of the known technical solutions Nuclear reactors contain, for control and accidental protection, bundled absorber rods (clusters) which are arranged longitudinally in fuel cassettes (BSK). The operating regime determines the time of removal, the characteristic of the highly activated cluster waste and the disposal costs. DD-WP 222997 proposes a method and a device for treating spent clusters until the production of containers capable of disposal.