Dose Assessment for Decommissioning Planning of the Greek Research Reactor Primary Cooling System
Abstract
Greek Research Reactor (GRR-1) is a light-water cooled and moderated heterogonous research reactor with a thermal output of 5 MW. The reactor is in extended shutdown for refurbishment since 2004. The refurbishment plan includes replacement of the Primary Cooling System. The decommissioning strategy consists of dismantling and removal of the bulky elements as whole pieces with-out preliminary segmentation and cutting and dis-mantling of the pipe works and PCS support structures. In this work the dose assessment and methodology in the context of planning for decommissioning of the PCS is presented.
Keywords
References
Apostolov T.G., Anastasova E.I., Anastasov V.D., Implementation of the partial dismantling of research reactor IRT-Sofia prior to its refurbish-ment. Nuclear Technology and Radiation Protec-tion, 25 (2010) 249-254.
Lobach, Yu.N., Shevel, V.N., Radiation protec-tion tasks on the Kiev’s research reactor WWR-M. Nuclear Technology and Radiation Protection 24 (2010) 145-151.
Katsoulas, G., Gikas, I., Kounenaki, K., Ko-kosouli, C, Cholis, C., Kormetzas, K., Savidou, A., Inventory and classification of the components and systems of the GRR-1 for decommissioning plan-ning, ibid.
Kontogeorgakos, D., Tzika, F., Valakis, S., Sta-matelatos, I. E. Occupational radiation exposure during removal of radioactive reactor components from GRR-1 pool. Radiation Protection Dosimetry, 144 (2011) 632-635.
Savidou, A., Stamatelatos, I.E., Non Destructive Technique to Verify Clearance of Pipes. Journal of Nuclear Technology Radiation Protection, 25, No. 2, (2010) 133-137.
Savidou A., Valakis S. T., Management of mate-rials that will arise from the dismantling of the Primary Cooling System of the GRR-1, Fresenius Environmental Bulletin, 22 (2013) 2027-2034.
EDF-6291 R 1, Radiological Characterization of the Engineering Test Reactor, Idaho Cleanup Pro-ject 09/12/06.
IAEA, International basic safety standards for protection against ionizing radiation and for the safety of radiation sources, Safety Series No 115, STI/PUB/996, ISBN 92-0-104295-7, Vienna, 1996.
Eckerman, K.F., Wolbarst, A.B., Richardson, A.C.B., Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Fac-tors for Inhalation, Submersion, and Ingestion, Rep. EPA-520/1-88-020, Federal Guidance Report No. 11, Environmental Protection Agency, Wash-ington DC (1988).
Brenk H. D., Investigation of Indoor-Inhalation Exposure due to Nuclear Accidents, Final Report for the Bundesminister fur Forschung und Tech-nologie, ISBN 3-924329-12-5, Aachen, 1987.
Refbacks
- There are currently no refbacks.
This work is licensed under a Creative Commons Attribution 3.0 License.
"No endorsement" policy: Unless explicitly stated otherwise, the opinions, analyses, discussions, views and recommendations outlined in the articles published in the International Nuclear Safety Journal (INSJ) are solely those of their respective authors and not of the editors, owners or publishers of the INSJ.