2 research outputs found
ΠΠΎΠ·Ρ ΠΎΠ±Π»ΡΡΠ΅Π½ΠΈΡ ΠΏΠ΅ΡΡΠΎΠ½Π°Π»Π° ΠΈ Π½Π°ΡΠ΅Π»Π΅Π½ΠΈΡ ΠΏΡΠΈ Π½ΠΎΡΠΌΠ°Π»ΡΠ½ΠΎΠΉ ΡΠΊΡΠΏΠ»ΡΠ°ΡΠ°ΡΠΈΠΈ ΠΏΡΠ½ΠΊΡΠΎΠ² Π·Π°Ρ ΠΎΡΠΎΠ½Π΅Π½ΠΈΡ ΡΠ°Π΄ΠΈΠΎΠ°ΠΊΡΠΈΠ²Π½ΡΡ ΠΎΡΡ ΠΎΠ΄ΠΎΠ²
This paper focuses on occupational and public exposure during operation of disposal facilities receiving liquid and solid radioactive waste of various classes and provides a comparative analysis of the relevant doses: actual and calculated at the design stage. Occupational and public exposure study presented in this paper covers normal operations of a radioactive waste disposal facility receiving waste. Results: Analysis of individual and collective occupational doses was performed based on data collected during operation of near-surface disposal facilities for short-lived intermediate-, lowand very low-level waste in France, as well as nearsurface disposal facilities for long-lived waste in Russia. Further analysis of occupational and public doses calculated at the design stage was completed covering a near-surface disposal facility in Belgium and deep disposal facilities in the United Kingdom and the Nizhne-Kansk rock massive (Russia). The results show that engineering and technical solutions enable almost complete elimination of internal occupational exposure, whereas external exposure doses would fall within the range of values typical for a basic nuclear facility. Conclusion: radioactive waste disposal facilities being developed, constructed and operated meet the safety requirements effective in the Russian Federation and consistent with relevant international recommendations. It has been found that individual occupational exposure doses commensurate with those received by personnel of similar facilities abroad. Furthermore, according to the forecasts, mean individual doses for personnel during radioactive waste disposal would be an order of magnitude lower than the dose limit of 20 mSv/year. As for the public exposure, during normal operation, potential impact is virtually impossible by delaminating boundaries of a nuclear facility sanitary protection zone inside which the disposal facility is located and can be solely attributed to the use of public roads during radioactive waste transportation to the disposal facility site.Β Π¦Π΅Π»Ρ ΡΠ°Π±ΠΎΡΡ β ΡΡΠ°Π²Π½ΠΈΡΠ΅Π»ΡΠ½ΡΠΉ Π°Π½Π°Π»ΠΈΠ· ΡΠ°ΠΊΡΠΈΡΠ΅ΡΠΊΠΈΡ
ΠΈ ΠΎΡΠ΅Π½ΠΈΠ²Π°Π΅ΠΌΡΡ
Π½Π° ΡΡΠ°ΠΏΠ΅ ΠΏΡΠΎΠ΅ΠΊΡΠΈΡΠΎΠ²Π°Π½ΠΈΡ Π΄ΠΎΠ· ΠΎΠ±Π»ΡΡΠ΅Π½ΠΈΡ ΠΏΠ΅ΡΡΠΎΠ½Π°Π»Π° ΠΈ Π½Π°ΡΠ΅Π»Π΅Π½ΠΈΡ ΠΏΡΠΈ Π·Π°Ρ
ΠΎΡΠΎΠ½Π΅Π½ΠΈΠΈ ΠΆΠΈΠ΄ΠΊΠΈΡ
ΡΠ°Π΄ΠΈΠΎΠ°ΠΊΡΠΈΠ²Π½ΡΡ
ΠΎΡΡ
ΠΎΠ΄ΠΎΠ² ΠΈ ΡΠ²Π΅ΡΠ΄ΡΡ
ΡΠ°Π΄ΠΈΠΎΠ°ΠΊΡΠΈΠ²Π½ΡΡ
ΠΎΡΡ
ΠΎΠ΄ΠΎΠ² ΡΠ°Π·Π»ΠΈΡΠ½ΡΡ
ΠΊΠ»Π°ΡΡΠΎΠ². Π ΡΠ°ΠΌΠΊΠ°Ρ
Π½Π°ΡΡΠΎΡΡΠ΅ΠΉ ΡΡΠ°ΡΡΠΈ ΡΠ°ΡΡΠΌΠ°ΡΡΠΈΠ²Π°Π΅ΡΡΡ Π²Π°ΡΠΈΠ°Π½Ρ ΠΎΠ±Π»ΡΡΠ΅Π½ΠΈΡ ΠΏΠ΅ΡΡΠΎΠ½Π°Π»Π° ΠΈ Π½Π°ΡΠ΅Π»Π΅Π½ΠΈΡ ΠΏΡΠΈ Π½ΠΎΡΠΌΠ°Π»ΡΠ½ΠΎΠΉ ΡΠΊΡΠΏΠ»ΡΠ°ΡΠ°ΡΠΈΠΈ ΠΏΡΠ½ΠΊΡΠ° Π·Π°Ρ
ΠΎΡΠΎΠ½Π΅Π½ΠΈΡ ΡΠ°Π΄ΠΈΠΎΠ°ΠΊΡΠΈΠ²Π½ΡΡ
ΠΎΡΡ
ΠΎΠ΄ΠΎΠ² Π² ΡΠ΅ΠΆΠΈΠΌΠ΅ ΡΠ°Π·ΠΌΠ΅ΡΠ΅Π½ΠΈΡ ΠΎΡΡ
ΠΎΠ΄ΠΎΠ². Π Π΅Π·ΡΠ»ΡΡΠ°ΡΡ: Π²ΡΠΏΠΎΠ»Π½Π΅Π½ Π°Π½Π°Π»ΠΈΠ· ΠΈΠ½Π΄ΠΈΠ²ΠΈΠ΄ΡΠ°Π»ΡΠ½ΡΡ
ΠΈ ΠΊΠΎΠ»Π»Π΅ΠΊΡΠΈΠ²Π½ΡΡ
Π΄ΠΎΠ· ΠΎΠ±Π»ΡΡΠ΅Π½ΠΈΡ ΠΏΠ΅ΡΡΠΎΠ½Π°Π»Π° ΠΏΡΠΈ ΠΏΡΠΈΠΏΠΎΠ²Π΅ΡΡ
Π½ΠΎΡΡΠ½ΠΎΠΌ Π·Π°Ρ
ΠΎΡΠΎΠ½Π΅Π½ΠΈΠΈ ΠΊΠΎΡΠΎΡΠΊΠΎΠΆΠΈΠ²ΡΡΠΈΡ
ΡΡΠ΅Π΄Π½Π΅Π°ΠΊΡΠΈΠ²Π½ΡΡ
, Π½ΠΈΠ·ΠΊΠΎΠ°ΠΊΡΠΈΠ²Π½ΡΡ
ΠΈ ΠΎΡΠ΅Π½Ρ Π½ΠΈΠ·ΠΊΠΎΠ°ΠΊΡΠΈΠ²Π½ΡΡ
ΡΠ°Π΄ΠΈΠΎΠ°ΠΊΡΠΈΠ²Π½ΡΡ
ΠΎΡΡ
ΠΎΠ΄ΠΎΠ² Π²ΠΎ Π€ΡΠ°Π½ΡΠΈΠΈ, Π° ΡΠ°ΠΊΠΆΠ΅ ΠΏΡΠΈ ΠΏΡΠΈΠΏΠΎΠ²Π΅ΡΡ
Π½ΠΎΡΡΠ½ΠΎΠΌ Π·Π°Ρ
ΠΎΡΠΎΠ½Π΅Π½ΠΈΠΈ Π΄ΠΎΠ»Π³ΠΎΠΆΠΈΠ²ΡΡΠΈΡ
ΡΠ°Π΄ΠΈΠΎΠ°ΠΊΡΠΈΠ²Π½ΡΡ
ΠΎΡΡ
ΠΎΠ΄ΠΎΠ² Π² Π ΠΎΡΡΠΈΠΈ. ΠΡΠΎΠ²Π΅Π΄Π΅Π½ Π°Π½Π°Π»ΠΈΠ· ΠΏΡΠΎΠ΅ΠΊΡΠ½ΡΡ
ΠΎΡΠ΅Π½ΠΎΠΊ Π΄ΠΎΠ· ΠΎΠ±Π»ΡΡΠ΅Π½ΠΈΡ ΠΏΠ΅ΡΡΠΎΠ½Π°Π»Π° ΠΈ Π½Π°ΡΠ΅Π»Π΅Π½ΠΈΡ Π΄Π»Ρ ΠΎΠ±ΡΠ΅ΠΊΡΠ° ΠΏΡΠΈΠΏΠΎΠ²Π΅ΡΡ
Π½ΠΎΡΡΠ½ΠΎΠΉ ΠΈΠ·ΠΎΠ»ΡΡΠΈΠΈ ΡΠ°Π΄ΠΈΠΎΠ°ΠΊΡΠΈΠ²Π½ΡΡ
ΠΎΡΡ
ΠΎΠ΄ΠΎΠ², ΠΏΠ»Π°Π½ΠΈΡΡΠ΅ΠΌΠΎΠ³ΠΎ ΠΊ ΡΠΎΠΎΡΡΠΆΠ΅Π½ΠΈΡ Π² ΠΠ΅Π»ΡΠ³ΠΈΠΈ, Π° ΡΠ°ΠΊΠΆΠ΅ ΠΏΡΠΎΠ΅ΠΊΡΠΈΡΡΠ΅ΠΌΡΡ
ΠΎΠ±ΡΠ΅ΠΊΡΠΎΠ² Π³Π»ΡΠ±ΠΈΠ½Π½ΠΎΠ³ΠΎ Π·Π°Ρ
ΠΎΡΠΎΠ½Π΅Π½ΠΈΡ Π² ΠΠ΅Π»ΠΈΠΊΠΎΠ±ΡΠΈΡΠ°Π½ΠΈΠΈ ΠΈ ΠΠΈΠΆΠ½Π΅ΠΊΠ°Π½ΡΠΊΠΎΠΌ ΠΌΠ°ΡΡΠΈΠ²Π΅ (Π ΠΎΡΡΠΈΠΉΡΠΊΠ°Ρ Π€Π΅Π΄Π΅ΡΠ°ΡΠΈΡ). Π’Π΅Ρ
Π½ΠΈΡΠ΅ΡΠΊΠΈΠΌΠΈ ΠΈ ΡΠ΅Ρ
Π½ΠΎΠ»ΠΎΠ³ΠΈΡΠ΅ΡΠΊΠΈΠΌΠΈ ΡΠ΅ΡΠ΅Π½ΠΈΡΠΌΠΈ ΡΠ΄Π°Π΅ΡΡΡ ΠΏΡΠ°ΠΊΡΠΈΡΠ΅ΡΠΊΠΈ ΠΏΠΎΠ»Π½ΠΎΡΡΡΡ ΠΈΡΠΊΠ»ΡΡΠΈΡΡ Π²Π½ΡΡΡΠ΅Π½Π½Π΅Π΅ ΠΎΠ±Π»ΡΡΠ΅Π½ΠΈΠ΅ ΠΏΠ΅ΡΡΠΎΠ½Π°Π»Π°, Π° Π΄ΠΎΠ·Ρ Π²Π½Π΅ΡΠ½Π΅Π³ΠΎ ΠΎΠ±Π»ΡΡΠ΅Π½ΠΈΡ ΠΎΠ³ΡΠ°Π½ΠΈΡΠΈΡΡ Π΄ΠΈΠ°ΠΏΠ°Π·ΠΎΠ½ΠΎΠΌ, Ρ
Π°ΡΠ°ΠΊΡΠ΅ΡΠ½ΡΠΌ ΠΈ Π΄Π»Ρ Π±Π°Π·ΠΎΠ²ΡΡ
ΡΠ΄Π΅ΡΠ½ΡΡ
ΡΠ΅Ρ
Π½ΠΎΠ»ΠΎΠ³ΠΈΠΉ. ΠΠ°ΠΊΠ»ΡΡΠ΅Π½ΠΈΠ΅: ΠΏΠ»Π°Π½ΠΈΡΡΠ΅ΠΌΡΠ΅ ΠΊ ΡΠΎΠΎΡΡΠΆΠ΅Π½ΠΈΡ, ΡΠΎΠΎΡΡΠΆΠ°Π΅ΠΌΡΠ΅ ΠΈ ΡΠΊΡΠΏΠ»ΡΠ°ΡΠΈΡΡΠ΅ΠΌΡΠ΅ ΠΏΡΠ½ΠΊΡΡ Π·Π°Ρ
ΠΎΡΠΎΠ½Π΅Π½ΠΈΡ ΡΠ΄Π°Π»ΡΠ΅ΠΌΡΡ
ΡΠ°Π΄ΠΈΠΎΠ°ΠΊΡΠΈΠ²Π½ΡΡ
ΠΎΡΡ
ΠΎΠ΄ΠΎΠ² ΡΠΎΠΎΡΠ²Π΅ΡΡΡΠ²ΡΡΡ Π΄Π΅ΠΉΡΡΠ²ΡΡΡΠΈΠΌ Π² Π ΠΎΡΡΠΈΠΈ ΡΡΠ΅Π±ΠΎΠ²Π°Π½ΠΈΡΠΌ Π±Π΅Π·ΠΎΠΏΠ°ΡΠ½ΠΎΡΡΠΈ, ΡΠΎΠ³Π»Π°ΡΡΡΡΠΈΠΌΡΡ Ρ ΠΌΠ΅ΠΆΠ΄ΡΠ½Π°ΡΠΎΠ΄Π½ΡΠΌΠΈ ΡΠ΅ΠΊΠΎΠΌΠ΅Π½Π΄Π°ΡΠΈΡΠΌΠΈ. ΠΡΠ΅Π½Π΅Π½ΠΎ, ΡΡΠΎ ΠΈΠ½Π΄ΠΈΠ²ΠΈΠ΄ΡΠ°Π»ΡΠ½ΡΠ΅ Π΄ΠΎΠ·Ρ ΠΎΠ±Π»ΡΡΠ΅Π½ΠΈΡ ΠΏΠ΅ΡΡΠΎΠ½Π°Π»Π° ΡΠΎΠΏΠΎΡΡΠ°Π²ΠΈΠΌΡ Ρ Π΄Π°Π½Π½ΡΠΌΠΈ ΠΊΠΎΠ½ΡΡΠΎΠ»Ρ ΠΏΠ΅ΡΡΠΎΠ½Π°Π»Π° Π°Π½Π°Π»ΠΎΠ³ΠΈΡΠ½ΡΡ
ΠΎΠ±ΡΠ΅ΠΊΡΠΎΠ² Π² Π΄ΡΡΠ³ΠΈΡ
ΡΡΡΠ°Π½Π°Ρ
. Π‘ΡΠ΅Π΄Π½ΠΈΠ΅ ΠΈΠ½Π΄ΠΈΠ²ΠΈΠ΄ΡΠ°Π»ΡΠ½ΡΠ΅ Π΄ΠΎΠ·Ρ ΠΎΠ±Π»ΡΡΠ΅Π½ΠΈΡ ΠΏΠ΅ΡΡΠΎΠ½Π°Π»Π° ΠΏΡΠΈ Π·Π°Ρ
ΠΎΡΠΎΠ½Π΅Π½ΠΈΠΈ ΡΠ°Π΄ΠΈΠΎΠ°ΠΊΡΠΈΠ²Π½ΡΡ
ΠΎΡΡ
ΠΎΠ΄ΠΎΠ² ΠΏΡΠΎΠ³Π½ΠΎΠ·ΠΈΡΡΡΡΡΡ Π½Π° ΠΏΠΎΡΡΠ΄ΠΎΠΊ Π½ΠΈΠΆΠ΅ ΡΡΡΠ°Π½ΠΎΠ²Π»Π΅Π½Π½ΠΎΠ³ΠΎ ΠΏΡΠ΅Π΄Π΅Π»Π° Π΄ΠΎΠ·Ρ β 20 ΠΌΠΠ²/Π³ΠΎΠ΄. ΠΠΎΠ·Π΄Π΅ΠΉΡΡΠ²ΠΈΠ΅ Π½Π° Π½Π°ΡΠ΅Π»Π΅Π½ΠΈΠ΅ ΠΏΡΠΈ Π½ΠΎΡΠΌΠ°Π»ΡΠ½ΠΎΠΉ ΡΠΊΡΠΏΠ»ΡΠ°ΡΠ°ΡΠΈΠΈ ΠΏΡΠ°ΠΊΡΠΈΡΠ΅ΡΠΊΠΈ ΠΈΡΠΊΠ»ΡΡΠ΅Π½ΠΎ ΡΡΡΠ°Π½ΠΎΠ²Π»Π΅Π½ΠΈΠ΅ΠΌ ΡΠ°Π½ΠΈΡΠ°ΡΠ½ΠΎ-Π·Π°ΡΠΈΡΠ½ΠΎΠΉ Π·ΠΎΠ½Ρ ΠΎΠ±ΡΠ΅ΠΊΡΠ° ΠΈΡΠΏΠΎΠ»ΡΠ·ΠΎΠ²Π°Π½ΠΈΡ Π°ΡΠΎΠΌΠ½ΠΎΠΉ ΡΠ½Π΅ΡΠ³ΠΈΠΈ, Π½Π° ΠΊΠΎΡΠΎΡΠΎΠΉ ΡΠ°Π·ΠΌΠ΅ΡΠ΅Π½Π° ΡΡΡΠ°Π½ΠΎΠ²ΠΊΠ° ΠΏΠΎ Π·Π°Ρ
ΠΎΡΠΎΠ½Π΅Π½ΠΈΡ ΠΎΡΡ
ΠΎΠ΄ΠΎΠ², ΠΈ Π²ΠΎΠ·ΠΌΠΎΠΆΠ½ΠΎ ΡΠΎΠ»ΡΠΊΠΎ ΠΏΡΠΈ ΡΡΠ°Π½ΡΠΏΠΎΡΡΠΈΡΠΎΠ²ΠΊΠ΅ ΡΠ°Π΄ΠΈΠΎΠ°ΠΊΡΠΈΠ²Π½ΡΡ
ΠΎΡΡ
ΠΎΠ΄ΠΎΠ² ΠΏΠΎ Π΄ΠΎΡΠΎΠ³Π°ΠΌ ΠΎΠ±ΡΠ΅Π³ΠΎ ΠΏΠΎΠ»ΡΠ·ΠΎΠ²Π°Π½ΠΈΡ ΠΊ ΠΌΠ΅ΡΡΡ ΡΠ°ΡΠΏΠΎΠ»ΠΎΠΆΠ΅Π½ΠΈΡ ΠΏΡΠ½ΠΊΡΠ° Π·Π°Ρ
ΠΎΡΠΎΠ½Π΅Π½ΠΈΡ ΡΠ°Π΄ΠΈΠΎΠ°ΠΊΡΠΈΠ²Π½ΡΡ
ΠΎΡΡ
ΠΎΠ΄ΠΎΠ².
Occupational and Public Exposure During Normal Operation of Radioactive Waste Disposal Facilities
This paper focuses on occupational and public exposure during operation of disposal facilities receiving liquid and solid radioactive waste of various classes and provides a comparative analysis of the relevant doses: actual and calculated at the design stage. Occupational and public exposure study presented in this paper covers normal operations of a radioactive waste disposal facility receiving waste. Results: Analysis of individual and collective occupational doses was performed based on data collected during operation of near-surface disposal facilities for short-lived intermediate-, lowand very low-level waste in France, as well as nearsurface disposal facilities for long-lived waste in Russia. Further analysis of occupational and public doses calculated at the design stage was completed covering a near-surface disposal facility in Belgium and deep disposal facilities in the United Kingdom and the Nizhne-Kansk rock massive (Russia). The results show that engineering and technical solutions enable almost complete elimination of internal occupational exposure, whereas external exposure doses would fall within the range of values typical for a basic nuclear facility. Conclusion: radioactive waste disposal facilities being developed, constructed and operated meet the safety requirements effective in the Russian Federation and consistent with relevant international recommendations. It has been found that individual occupational exposure doses commensurate with those received by personnel of similar facilities abroad. Furthermore, according to the forecasts, mean individual doses for personnel during radioactive waste disposal would be an order of magnitude lower than the dose limit of 20 mSv/year. As for the public exposure, during normal operation, potential impact is virtually impossible by delaminating boundaries of a nuclear facility sanitary protection zone inside which the disposal facility is located and can be solely attributed to the use of public roads during radioactive waste transportation to the disposal facility site