Kazakhstan’s BN-350 fast reactor was shut down in 1999 and is in the process of being decommissioned in preparation for Safestore. A key achievement during 2010 was the removal of the known inventory of spent nuclear fuel (SNF) from the reactor to off-site secure storage. As a complementary activity, surveys of areas of the fuel discharge route where it was considered possible for fuel pins or fuel residues to have collected over many years of operation were also arranged to confirm that no significant amounts of fuel of remained at the plant. This paper reports on the remote radiation and visual (video and still photograph) surveys undertaken on the following areas of the BN-350 spent fuel route: • The waste storage repository or vault underneath the Post-Irradiation Examination Hot Cell in which non-destructive and destructive examination of irradiated fuels was undertaken throughout the operating life of the reactor. • The fuel transfer and washing cells within which irradiated fuel sub-assemblies were processed and residual sodium coolant removed. • The fuel storage ponds. Man access to several areas (particularly the waste vault) was not possible due to very high radiation levels from stored βγ-active wastes or residual contamination and in these cases specially engineered remote camera and radiation detector deployment systems were developed and used. In other areas, such as the ponds, limited man access was possible under prepared and controlled conditions. The survey results, together with associated radiochemical and radiation dose rate analysis, demonstrated that, despite several recorded handling incidents during Hot Cell operations, the maximum estimated amounts of nuclear material which could remain at BN-350 were sufficiently low to give no major safeguards concerns. The data also provides key information to guide decommissioning and dismantling planning in the future.
Skip Nav Destination
ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management
September 25–29, 2011
Reims, France
Conference Sponsors:
- Nuclear Engineering Division and Environmental Engineering Division
ISBN:
978-0-7918-5498-3
PROCEEDINGS PAPER
Remote Radiation and Visual Surveys of the Hot Cell Waste Vault and Spent Fuel Transfer Route at Kazakhstan’s BN-350 Reactor
David Wells,
David Wells
Nuvia Limited, Dorchester, Dorset, UK
Search for other works by this author on:
Andrew Herrick,
Andrew Herrick
Nuvia Limited, Thurso, Caithness, Scotland
Search for other works by this author on:
Alexander Klepikov,
Alexander Klepikov
Nuclear Technology Safety Center, Almaty, Kazakhstan
Search for other works by this author on:
Igor Yakovlev,
Igor Yakovlev
MAEC-Kazatomprom, Aktau, Kazakhstan
Search for other works by this author on:
Evgeniy Tur,
Evgeniy Tur
National Nuclear Center RK, Kurchatov, Kazakhstan
Search for other works by this author on:
Collin Knight
Collin Knight
Idaho National Laboratory, Idaho Falls, ID
Search for other works by this author on:
David Wells
Nuvia Limited, Dorchester, Dorset, UK
Andrew Herrick
Nuvia Limited, Thurso, Caithness, Scotland
Alexander Klepikov
Nuclear Technology Safety Center, Almaty, Kazakhstan
Igor Yakovlev
MAEC-Kazatomprom, Aktau, Kazakhstan
Evgeniy Tur
National Nuclear Center RK, Kurchatov, Kazakhstan
Collin Knight
Idaho National Laboratory, Idaho Falls, ID
Paper No:
ICEM2011-59101, pp. 1313-1321; 9 pages
Published Online:
August 17, 2012
Citation
Wells, D, Herrick, A, Klepikov, A, Yakovlev, I, Tur, E, & Knight, C. "Remote Radiation and Visual Surveys of the Hot Cell Waste Vault and Spent Fuel Transfer Route at Kazakhstan’s BN-350 Reactor." Proceedings of the ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B. Reims, France. September 25–29, 2011. pp. 1313-1321. ASME. https://doi.org/10.1115/ICEM2011-59101
Download citation file:
8
Views
Related Proceedings Papers
Related Articles
Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study
ASME J of Nuclear Rad Sci (April,2023)
Thermal Analysis of Irradiated Fuel Subassemblies and Fuel Pins During Storage in Concrete Pits of Head-End Facility
J. Thermal Sci. Eng. Appl (March,2016)
FAST Code System: Review of Recent Developments and Near-Future Plans
J. Eng. Gas Turbines Power (October,2010)
Related Chapters
Characterization
Decommissioning Handbook
Utilities’ Perspective of Spent Fuel Storage
Global Applications of the ASME Boiler & Pressure Vessel Code
Spent Fuel and Decommissioning
Decommissioning Handbook