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Provision of the radiation safety for the decomissioning of the heavy-water research nuclear reactor NRC «Kurchatov Institute» – ITEP

Authors :
I. V. Mednikov
V. V. Vasilyev
A. S. Busygin
A. A. Sobko
Source :
Радиационная гигиена, Vol 13, Iss 1, Pp 74-83 (2020)
Publication Year :
2020
Publisher :
Saint-Petersburg Research Institute of Radiation Hygiene after Professor P.V. Ramzaev, 2020.

Abstract

The article provides a brief description of organizational and technical measures aimed at ensuring radiation safety during the decommissioning of the heavy-water research nuclear reactor of Institute for Theoretical and Experimental Physics after A.I. Alikhanov of National Research Centre «Kurchatov Institute». Information is provided on the history and features of the operation of the reactor, including parameters and characteristics that are significant for planning and conducting work. The peculiarities of legal regulation in the field of ensuring radiation safety are given; regulatory acts and rules accompanying other activities during decommissioning and directly related to radiation safety are also considered. The paper describes the work done in preparation for dismantling, the initial and current state of the installation, forthcoming work with examples of dismantled equipment. Methods for handling radioactive waste arising during decommissioning are considered, including methods for fragmentation of large structural elements (examples of mechanical devices are given), methods for sorting according to different specific activity (high activity, low activity), radionuclide composition and physical properties (solid, metallic, non-metallic, liquid). A special method for handling liquid radioactive waste is described, which includes the collection and temporary storage system. To assess the radiation situation at workplaces during the dismantling of the reactor structures, calculations of radiation transfer were carried out on the running and shutdown reactor, during which it was established that the expected dose to the personnel when performing activities on decommissioning of TBR is much lower than the limit values, established by regulatory documents. In accordance with the estimated radiation doses, rules and instructions for personnel were determined, including the procedure for using personal protective equipment, the necessary measures for surface decontamination, etc. Information is given on the procedure for radiation monitoring at all stages of dismantling and at the final stages of decommissioning including control of premises, personnel, equipment, waste of various types, atmospheric air.

Details

Language :
English, Russian
ISSN :
1998426X
Volume :
13
Issue :
1
Database :
Directory of Open Access Journals
Journal :
Радиационная гигиена
Publication Type :
Academic Journal
Accession number :
edsdoj.02d2cdc3ce454e92bb664393ebdd2c2b
Document Type :
article
Full Text :
https://doi.org/10.21514/1998-426X-2020-13-1-74-83