Cel THE OBJECTIVES OF THE PROJECT ARE TO PILOT THE DEVELOPMENT OF TECHNOLOGY FOR THE DECOMMISSIONING OF FACILITIES USED IN THE FABRICATION OF MIXED-OXIDE FUELS. BASED ON EXISTING EXPERIENCE, THE AIM IS TO ESTABLISH THE PROCEDURES WHICH ARE THE MOST COST-EFFECTIVE OVERALL UNDER THE SPECIFIC CONTRAINTS ON THE DISPOSAL OF WASTES ARISING AND ON THE RADIATION EXPOSURE OF PERSONNEL. THE DEVELOPMENT PROGRAMME IS INTEGRATED WITHIN THE DECOMMISSIONING OF THE CO-PRECIPITATION PLANT WHICH WAS USED TO PRODUCE MIXED-OXIDE POWDER FOR THE FABRICATION OF FAST REACTOR FUEL. THE PLANT IS ON TWO FLOORS AND OCCUPIES A TOTAL FLOOR AREA OF SOME 320 M2 WITHIN WHICH ARE HOUSED 14 GLOVE BOXES, 2 FURNACES, 5 TANKS, A SCRUBBER VESSEL, VENTILATION DUCTING AND PIPEWORK. THE TECHNIQUES TO BE TESTED ARE THOSE WHICH MEET THE SPECIFIC CONSTRAINTS AND FOR WHICH PREVIOUS RESEARCH HAS INDICATED THE POTENTIAL FOR LARGE-SCALE APPLICATION. DECONTAMINATION DISMANTLING AND PACKAGING OF THE WASTES ARE THE OPERATIONS INVOLVED WHILE THE RADIATION, CONTAMINATION AND INGESTION HAZARDS IMPOSE RESTRICTIONS ON THE METHODS OF WORKING. IT IS TOWARDS THE MOST EFFECTIVE OVERALL PROCEDURE THAT THE TECHNIQUES WILL BE CONCERTED. INCLUDED IN THE ASPECTS OF THIS DEVELOPMENT ARE THE MINIMISING OF THE AMOUNT OF ALPHA-CONTAMINATED WASTE MATERIAL, THE MINIMISING OF THE RADIATION EXPOSURE TO PERSONNEL, THE IDENTIFICATION OF THE BEST MEANS OF IN-SITU DECONTAMINATION., AND THE MOST SUITABLE MEANS OF MEASURING IN-SITU THE ALPHA CONTAMINATION. FINALLY, A COMPARISON OF COSTS AND RADIATION EXPOSURE FROM ALTERNATIVE TECHNIQUES IN THE REAL APPLICATION OF DECOMMISSIONING WILL BE MADE. Decommissioning of the coprecipitation plant, which made plutonium and uranium oxide fuel, is a lead study in the decommissioning programme. The overall programme has the objectives of gaining data and experience in a wide range of decommissioning operations and hence, in this specific study, to pilot the decommissioning of plant heavily contaminated with plutonium and other actinides. Consequently the operations have been used to test improvements in temporary containment, contamination control and decontamination techniques and also to develop an in situ plutonium assay, plutonium recovery and size reduction techniques. Finally, the work is also yielding data on manpower requirements, personnel radiation uptake and waste generated to help in the planning of future decommissioning work.B.1. DETAILED PLANNING FOR MOST APPROPRIATE DECONTAMINATION AND DISMANTLING, INCLUDING TECHNICAL SPECIFICATIONS AND SAFETY ASSESSMENTS FOR PROPOSED METHODS AND PLANT MODIFICATIONS AND SUBMISSIONS FOR COMPANY AND REGULATORY APPROVALS. B.2. EXECUTION OF MODIFICATIONS, TESTING OF EQUIPMENT, REHEARSING OF PROPOSED PROCEDURES ON PLANT SIMULATIONS, FOLLOWED BY IN-SITU DECONTAMINATION. B.3. REHEARSING OF DISMANTLING AND PACKAGING PROCEDURES ON PLANT SIMULATIONS, FOLLOWED BY IN-SITU DISMANTLING AND PACKAGING. Dziedzina nauki engineering and technologyenvironmental engineeringenergy and fuels Program(-y) FP1-DECOM 2C - Research programme (Euratom) concerning the decommissioning of nuclear installations, 1984-1988 Temat(-y) Data not available Zaproszenie do składania wniosków Data not available System finansowania CSC - Cost-sharing contracts Koordynator BRITISH NUCLEAR FUELS PLC Wkład UE Brak danych Adres Hinton House, Risley WA3 6AS WARRINGTON Zjednoczone Królestwo Zobacz na mapie Koszt całkowity Brak danych
