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Decommissioning of Shielded Facilities at Winfrith Used for Post Irradiation Examination of Nuclear Fuels and Other Active Items.

DE2005826080

Publication Date	2003
Personal Author	Miller, K. D.; Parkinson, S. J.; Cornell, R. M.
Page Count	16
Abstract	This paper describes the approaches used in the clearing, cleaning, decontamination and decommissioning of a very large suite of seven concrete shielded caves and other facilities used by UKAEA at Winfrith Technology Centre, England over a period of about 30 years for the post-irradiation examination (PIE) of a wide range of nuclear fuels and other very active components. The basic construction of the facilities will first be described, setting the scene for the major challenges that 1970s' thinking posed for decommissioning engineers. The tendency then to use large and heavy items of equipment supported upon massive steel bench structures produced a series of major problems that had to be overcome. The means of solving these problems by utilization of relatively simple and inexpensive equipment will be described. Later, a further set of challenges was experienced to decontaminate the interior surfaces to allow man entries to be undertaken at acceptable dose rates. The paper will describe the types of tooling used and the range of complementary techniques that were employed to steadily reduce the dose rates down to acceptable levels. Some explanations will also be given for the creation of realistic dose budgets and the methods of recording and continuously assessing the progress against these budgets throughout the project. Some final considerations are given to the commercial approaches to be adopted throughout this major project by the decommissioning engineers. Particular emphasis will be given to the selection of equipment and techniques that are effective so that the whole process can be carried out in a cost-effective and timely manner. The paper also provides brief complementary information obtained during the decommissioning of a plutonium-contaminated facility used for a range of semi-experimental purposes in the late 1970s. The main objective here was to remove the alpha contamination in such a manner that the volume of Plutonium Contaminated Materials (PCM) was minimized and to clean the whole facility to a free-breathing state such that it would be available for other work or subsequent demolition.
Keywords	Radioactive waste management Decommissioning Decontamination Caves Schematic diagrams Concrete structures Nuclear industry Waste management Equipment Techniques Cost-effectiveness Waste disposal Dose rates Nuclear fuels Meetings United Kingdom Atomic Energy Authority (UKAEA) Post-irradiation examination (PIE)
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	UKAEA, Harwell (England). Atomic Energy Research Establishment.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200521

Decommissioning of Shielded Facilities at Winfrith Used for Post Irradiation Examination of Nuclear Fuels and Other Active Items.

Decommissioning of Shielded Facilities at Winfrith Used for Post Irradiation Examination of Nuclear Fuels and Other Active Items.
DE2005826080

Publication Date	2003
Personal Author	Miller, K. D.; Parkinson, S. J.; Cornell, R. M.
Page Count	16
Abstract	This paper describes the approaches used in the clearing, cleaning, decontamination and decommissioning of a very large suite of seven concrete shielded caves and other facilities used by UKAEA at Winfrith Technology Centre, England over a period of about 30 years for the post-irradiation examination (PIE) of a wide range of nuclear fuels and other very active components. The basic construction of the facilities will first be described, setting the scene for the major challenges that 1970s' thinking posed for decommissioning engineers. The tendency then to use large and heavy items of equipment supported upon massive steel bench structures produced a series of major problems that had to be overcome. The means of solving these problems by utilization of relatively simple and inexpensive equipment will be described. Later, a further set of challenges was experienced to decontaminate the interior surfaces to allow man entries to be undertaken at acceptable dose rates. The paper will describe the types of tooling used and the range of complementary techniques that were employed to steadily reduce the dose rates down to acceptable levels. Some explanations will also be given for the creation of realistic dose budgets and the methods of recording and continuously assessing the progress against these budgets throughout the project. Some final considerations are given to the commercial approaches to be adopted throughout this major project by the decommissioning engineers. Particular emphasis will be given to the selection of equipment and techniques that are effective so that the whole process can be carried out in a cost-effective and timely manner. The paper also provides brief complementary information obtained during the decommissioning of a plutonium-contaminated facility used for a range of semi-experimental purposes in the late 1970s. The main objective here was to remove the alpha contamination in such a manner that the volume of Plutonium Contaminated Materials (PCM) was minimized and to clean the whole facility to a free-breathing state such that it would be available for other work or subsequent demolition.
Keywords	Radioactive waste management Decommissioning Decontamination Caves Schematic diagrams Concrete structures Nuclear industry Waste management Equipment Techniques Cost-effectiveness Waste disposal Dose rates Nuclear fuels Meetings United Kingdom Atomic Energy Authority (UKAEA) Post-irradiation examination (PIE)
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	UKAEA, Harwell (England). Atomic Energy Research Establishment.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200521