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Assessment of public exposure

All the efforts are made for assessment of public exposure due to different sources: radionuclides in foodstuff and drinking water, terrestrial radionuclides, construction materials, indoor radon. In case of necessity assessment of exposure is done in special cases, due to some specific sources.


Dose limits and dose constraints for members of public are given in radiation protection legislation. Main requirements of public evaluation are fixed in Hygiene Standard HN 73:2018 “Basic Standard of Radiation Protection” adopted by the Order No. 663 on 21 December 2001 by the Minister of Health Care.


Program dedicated to public exposure monitoring was approved by the Order No. V-414 of Minister of Health Care of 12 April 2017 for years 2017–2023. Program includes public monitoring measures to estimate exposure due all possible sources of ionizing radiation that has influence to man and to see the trends of exposure, identify sources that cause main constituent part of exposure and to take recommendations for optimization of public exposure.


Maximum permitable levels of radionuclides in foodstuffs are regulated in Council Regulation (EC) No 733/2008 of 15 July 2008(OL L 201, 2008-07-30, p. 1) on the conditions governing imports of agricultural products originating in third countries following the accident at the Chernobyl nuclear power station and Council Regulation (EC) No 1048/2009 of 23 October 2009 amending Regulation (EC) No 733/2008.


Requirements of foodstuffs imported form Japan are fixed in Commission Implementing Regulation (EU) No 351/2011of 11 April 2011 imposing special conditions governing the import of feed and food originating in or consigned from Japan following the accident at the Fukushima nuclear power station (OL L 97, 2011-04-12, p. 20).


Radiological impact assesment of nuclear facilities


Ignalina Nuclear Power Plant (Ignalina NPP)

Ignalina NPP is located at the periphery of Lithuanian East, near the borders with Belorus and Latvia and constructed on the southern coast of Druksiai Lake. The first unit of the plant was commissioned on 31st of December 1983, the second one – on 15th August 1987.

Currently the RBMK-1500 (Reaktor bolshoj moshnnosti kanalnyj) water-cooled graphite-moderated channel-type power reactors of Ignalina nuclear power plant are stopped. The first unit of Ignalina NPP was finally stopped on 31st of December 2004, the second unit – on the end of 2009. The preparation for dismantling of the first unit is ongoing. For more information see the official Ignalina AE webpage.


Decommissioning of Ignalina NPP


The decommissioning of the nuclear facilities is the final stage of their life cycle. It is one of the most complicated processes, which needs thoroughly preparation and shall be handled with particular care.

Decommissioning of a nuclear facility consists of implementation of legal, organisational and technical measures to manage the nuclear facility, when the decision for shutdown is adopted and the facility do not operate for the main purpose.

The first unit of Ignalina NPP has been finally stopped on 31st of December 2004. The second unit was finally stopped on 31st of December 2009.


Radiation protection of general public


NPP remains a potentially dangerous site due to the discharges of radionuclides into the environment during decommissioning works. According to the NPP report the activity of radioactive aerosols discharged into the environment in 2017 was 54•106 Bq, far below the limited activity (activity limit – 1.7∙1012 Bq/year). No discharges of radioactive inert gas and radioactive 131I into the environment produced. Small amount 9.6∙105 Bq of 60Co (activity limit – 5.0∙109 Bq/year) and 27.9∙106 Bq 137Cs (activity limit – 3.3∙1010 Bq/year) were discharged into the lake Drūkšiai. In 2017, the annual effective dose of the member of the critical group due to radionuclide discharges to the atmosphere and water was 0.07 μSv, significantly lower than the dose constraint (0.2 mSv/ year). 


Closed Maišiagala radioactive waste storage facility

The Mašiagala radon type storage facility has been operated from 1963 to 1988. In this facility radwaste generated in medicine, industry, science and education facilities was placed. Radwaste consists of calibration instruments, chemical compounds, charge eliminators, high activity gamma sources, smoke detectors, solid radwaste (such as plastic, special closes, wood etc.). The facility consists of a subsurface concrete vault (See fig. 1) with an overall volume of about 200 m3. The vault was filled to about 60%. Vault was grouted inside the disposal cells and the repository has been covered by a concrete blocks, bitumen, asphalt and earth.

RPC analyzes and evaluates radiological environmental monitoring data of Maišiagala facility. RATA carries out environmental monitoring and provides quarterly and annual reports to RPC.

Noticeable decrease of tritium activity in control wells (located around the facility) is related to upgrading works of Maišiagala facility – installed engineered barriers reduced infiltration of rainfall and migration of radionuclides in to groundwater.  

Last update 16 February 2019

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The web site was updated under the auspices of Swedish Radiation Safety Institution (now SSM)