The BR3 plant at Mol in Belgium built at the end of the fifties was the first PWR plant built outside the USA. The reactor had a small net power output (10 MWe) but comprised all the loops and features of a commercial PWR plant. The BR3 plant was operated with the main objective of testing advanced PWR fuels under irradiation conditions similar to those encountered in large commercial PWR plants. The reactor was started in 1962 and shut down in 1987 after 25 years of continuous operation. Since 1989, SCK•CEN is decommissioning the BR3 PWR research reactor. The dismantling of the metallic components including reactor pressure vessel and internals is completed and extensively reported in the literature. The dismantling of auxiliary components and the decontamination of parts of the infrastructure are now going on. The decommissioning progress is continuously monitored and costs and strategy are regularly reassessed. The first part of the paper describes the main results and lessons learned from the reassessment exercises performed in 1994, 1999, 2004 and 2007. Impacts of changes in legal framework on the decommissioning costs will be addressed. These changes concern e.g. licensing aspects, clearance levels, waste management… The middle part of the paper discusses the management of activated and/or contaminated concrete. The costing exercise performed in 1995 highlighted that the management of activated and contaminated concrete is the second main cost item after the dismantling of the reactor pressure vessel and internals. Different possible solutions were studied. These are evacuation as radioactive waste with or without supercompaction, recycling this “radioactive” grout or concrete for conditioning of radioactive waste e.g. conditioning of metallic waste. The paper will give the results of the cost-benefit analysis made to select the solution retained. The last part of the paper will discuss the end goal of the decommissioning of the BR3. In the final decommissioning plan approved by ONDRAF/NIRAS, it was mentioned that the final goal of the BR3 decommissioning will be the “green field” unless opportunities for reuse of the BR3 site will occur during decommissioning. A strategy of partial reuse of the BR3 facility is proposed and being discussed with the main stakeholders. The paper will give the present state of the discussion.
Skip Nav Destination
The 11th International Conference on Environmental Remediation and Radioactive Waste Management
September 2–6, 2007
Bruges, Belgium
Conference Sponsors:
- Nuclear Division and Environmental Engineering Division
ISBN:
978-0-7918-4339-0
PROCEEDINGS PAPER
Decommissioning of the BR3 Reactor: Status and Perspectives Available to Purchase
I. Verstraeten
I. Verstraeten
NIRAS/ONDRAF, Brussels, Belgium
Search for other works by this author on:
L. Noynaert
SCK•CEN, Mol, Belgium
I. Verstraeten
NIRAS/ONDRAF, Brussels, Belgium
Paper No:
ICEM2007-7128, pp. 551-555; 5 pages
Published Online:
May 29, 2009
Citation
Noynaert, L, & Verstraeten, I. "Decommissioning of the BR3 Reactor: Status and Perspectives." Proceedings of the The 11th International Conference on Environmental Remediation and Radioactive Waste Management. 11th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B. Bruges, Belgium. September 2–6, 2007. pp. 551-555. ASME. https://doi.org/10.1115/ICEM2007-7128
Download citation file:
19
Views
Related Proceedings Papers
Related Articles
The Fabulous Nuclear Odyssey of Belgium
J. Pressure Vessel Technol (June,2009)
NED Chair's Message
ASME J of Nuclear Rad Sci (January,2024)
Heat Transfer Within a Steel-Reinforced Porous Concrete Slab Subjected to Microwave Heating
J. Heat Transfer (August,1995)
Related Chapters
NRC Requirements for Decommissioning
Decommissioning Handbook
Dismantling
Decommissioning Handbook
Functionality and Operability Criteria
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 2, Third Edition