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Control of the working environment dosimetry and technical radiation protection at the RA reactor, Part I; Deo I: Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA

Abstract

This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted to 16.9 mSV during past 10 months. Individual exposures for 9/10 of the personnel were less than 1/10 of the permissible annual exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. The last part analyzes accidents occurred at the reactor during 1984. It was found that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel.
Authors:
Ninkovic, N; Bjelanovic, J; Minicic, Z; Komatina, R; Raicevic, J [1] 
  1. Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)
Publication Date:
Dec 15, 1984
Product Type:
Technical Report
Report Number:
INIS-RS-0665
Resource Relation:
Other Information: 8 tabs. 22 figs; Related Information: In: RA Research nuclear reactor, Part II - radiation protection at the RA nuclear reactor in 1984, Istrazivacki nuklearni reaktor RA - Deo II - zastita od zracenja kod nuklearnog reaktora RA u 1984. godini, by Ninkovic, M.; Ajdacic, N.; Zaric, M.; Vukovic, Z. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)], 117 pages.
Subject:
61 RADIATION PROTECTION AND DOSIMETRY; DECONTAMINATION; DOSIMETRY; MAXIMUM PERMISSIBLE EXPOSURE; R-A REACTOR; RADIATION MONITORING; RADIATION PROTECTION; RADIOACTIVE EFFLUENTS; RADIOACTIVE WASTES; SURFACE CONTAMINATION
OSTI ID:
20901491
Research Organizations:
Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)
Country of Origin:
Serbia
Language:
English
Other Identifying Numbers:
TRN: RS07RA250063737
Availability:
Available from INIS in electronic form; Also available from the Institute of nuclear sciences Vinca
Submitting Site:
INIS
Size:
page(s) 39
Announcement Date:
Aug 30, 2007

Citation Formats

Ninkovic, N, Bjelanovic, J, Minicic, Z, Komatina, R, and Raicevic, J. Control of the working environment dosimetry and technical radiation protection at the RA reactor, Part I; Deo I: Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA. Serbia: N. p., 1984. Web.
Ninkovic, N, Bjelanovic, J, Minicic, Z, Komatina, R, & Raicevic, J. Control of the working environment dosimetry and technical radiation protection at the RA reactor, Part I; Deo I: Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA. Serbia.
Ninkovic, N, Bjelanovic, J, Minicic, Z, Komatina, R, and Raicevic, J. 1984. "Control of the working environment dosimetry and technical radiation protection at the RA reactor, Part I; Deo I: Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA." Serbia.
@misc{etde_20901491,
title = {Control of the working environment dosimetry and technical radiation protection at the RA reactor, Part I; Deo I: Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA}
author = {Ninkovic, N, Bjelanovic, J, Minicic, Z, Komatina, R, and Raicevic, J}
abstractNote = {This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted to 16.9 mSV during past 10 months. Individual exposures for 9/10 of the personnel were less than 1/10 of the permissible annual exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. The last part analyzes accidents occurred at the reactor during 1984. It was found that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel.}
place = {Serbia}
year = {1984}
month = {Dec}
}