Retrieval and conditioning of graphite legacy waste in La Hague plant - 000105
Creators
- 1. Orano Cycle La Hague, - 50440 Beaumont-Hague (France)
- 2. Orano Projets, 1 rue des Herons - 78182 Saint-Quentin-Yvelines Cedex (France)
- 3. Orano Dismantling and Waste Management Division, 1 place Jean Millier - 92400 Courbevoie (France)
Description
The UP2-400 reprocessing plant at La Hague, France, was commissioned in 1967, and operated until 1998. Over the period, it has processed over 9500 tons of fuel, 5000 tons of which were gas cooled natural uranium fuel (UNGG). During that period, graphite sleeves and magnesium cladding separated from the fuel elements were stored together in two large silos, with some eventual other solid waste. The accumulated total amounted to 1100 tons at the end of the period. The aim of the RCD UNGG 130 Project is to remove all the wastes from Silo 130. Retrieval will be performed in 4 main stages, aiming at optimizing schedule and hazard reduction. In the first stage the bulk of the waste is retrieved. A cable-driven harrow is used to move the waste within the silo towards the retrieval gripper. In the second stage the incoming waste is emptied on a rinsing and size separation table, where the waste pieces are separated according to their size though a vibrating screen with a 15 mm mesh. The finer pieces are evacuated directly into the canister. The bulkiest fragments are transferred and piled into a receiving tank. At this stage, each remaining piece needs to be staged individually. This is done using a picking robot. Once the object has been selected by the robot, it passes through a laser line and is scanned simultaneously by two cameras located above the conveyor. A 3D image is built and submitted to a pattern recognition software which is then able to compare the image to a databank and classify the object. When the software recognizes aluminum pieces, the conveyor automatically stops and the object is removed by the operator with the help of a remote manipulator. When the software recognizes a piece of magnesium (cap or slider), a conventional (upper bound) surface area is recorded and the object is introduced into the storage container. The last step involves the final operations. All kind of waste is introduced into the container (mostly crushed graphite and magnesium) with the exception of aluminium and bulky operational waste. Once the canister is filled with waste and demineralized water, sodium hydroxide and lime are added and the solution is recirculated to homogenize the mixture. The canister is then capped with a vented cover prior to control and dispatching to the interim storage facility. (authors)
Files
Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- INIS-FR--19-0632
Conference
- Title
- International conference on dismantling challenges: industrial reality, prospects and feedback experience
- Acronym
- DEM 2018
- Dates
- 22-24 Oct 2018
- Place
- Avignon (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 50033955
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM; AREVA NC LA HAGUE; GRAPHITE; MAGNESIUM; RADIOACTIVE WASTE MANAGEMENT; SORTING; SPENT FUELS
- Descriptors DEC
- ALKALINE EARTH METALS; AREVA NC; CARBON; ELEMENTS; ENERGY SOURCES; FRENCH ORGANIZATIONS; FUEL REPROCESSING PLANTS; FUELS; MANAGEMENT; MATERIALS; METALS; MINERALS; NATIONAL ORGANIZATIONS; NONMETALS; NUCLEAR FACILITIES; NUCLEAR FUELS; REACTOR MATERIALS; WASTE MANAGEMENT
Optional Information
- Notes
- Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses