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LARGE WASTE CONTAINERS CAST OF LOW-LEVEL RADIOACTIVE METAL SCRAP.

Ziel

RADIOACTIVE WASTE COMING FROM DISMANTLING OF LARGE REACTOR COMPONENTS SHOULD BE TRANPORTED IN LARGER CONTAINERS THAN THOSE ALREADY USED, IN ORDER TO SAVE CUTTING WORK AND, CONSEQUENTLY, RADIATION EXPOSURE OF PERSONNEL. THE USE OF RADIOACTIVE STEEL FOR MANUFACTURING TRANSPORT AND DISPOSAL CONTAINERS REDUCES THE VOLUME OF WASTE TO BE STORED, AND ALSO METAL CONSUMPTION.

A REFERENCE CONTAINER WILL BE CHOSEN IN AGREEMENT WITH REQUIREMENTS FOR THE KONRAD DISPOSAL SITE AND SUITABLE FOR FABRICATION OUT OF LOW-LEVEL RADIOACTIVE STEEL (SPECIFIC ACTIVITY UP TO 74 BQ/G).

IN A SUPPLEMENTARY AGREEMENT CONCLUDED IN 1988, THE INITIAL WORK PROGRAMME WAS EXTENDED TO STUDIES RELATED TO THE QUALIFICATION REQUIREMENTS FOR WASTE CONTAINERS, PRESENTLY UNDER DEVELOPMENT AT THE PHYSIKALISCH-TECHNISCHE BUNDESANSTALT (PTB). THIS WILL BE APPLIED TO THE AVAILABLE PROTOTYPE CONTAINER WACO I.

B.1. OPTIMISATION OF TYPE A CAST STEEL CONTAINERS, TAKING INTO ACCOUNT ALL RELEVANT REQUIREMENTS FOR SAFE TRANSPORT AND DISPOSAL IN THE KONRAD MINE.

B.2. DESIGN OF A PROTOTYPE CONTAINER BASED ON THE PREVIOUS OPTIMISATION.

B.3. FABRICATION OF THE PROTOTYPE CONTAINER WITH LID AND ALL ACCESSORIES (PLUGS, SEALING, SCREWS...) AND TESTING UNDER BOUNDARY CONDITIONS AS GIVEN BY IAEA AND GERMAN REGULATIONS.

B.4. ESTABLISHMENT OF A RADIOLOGICAL MEASUREMENT PROGRAMME AND MEASURING OF ALL RELEVANT ACTIVITIES OCCURING BEFORE AND DURING FABRICATION, AND ON THE FINISHED CONTAINER.

B.5. DESIGN STUDIES AND EXPERIMENTS AIMING AT OPTIMISING THE PROTOTYPE AS REGARDS LEAKTIGHTNESS AND THE POTENTIAL FOR REPAIRS.

B.6. FIVE EXPERIMENTS ON THE PROTOTYPE WITH A VIEW TO ASSESSING LEAKTIGHTNESS AND MECHANICAL INTEGRITY.

B.7. DEFINITION OF THE ORIGINAL STATUS AND BACKFITTING OF THE PROTOTYPE WITH ABOVE DEVELOPED METHODS.

B.8. RADIOLOGICAL STUDIES INTO THE HEALTH PHYSICS CONSEQUENCES FOR GIVEN RELEASE RATE AND ACTIVITY INVENTORIES.

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