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Assess of the need for waste water treatment plant of the uranium - - PowerPoint PPT Presentation

Ministry of Health National Centre of Radiobiology and Radiation Protection Sofia - Bulgaria Assess of the need for waste water treatment plant of the uranium mining site Iskra, Katina Kremena Ivanova Radostina Georgieva SITE


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Assess of the need for waste water treatment plant of the uranium mining site “Iskra”, Katina

Kremena Ivanova Radostina Georgieva

Ministry of Health National Centre of Radiobiology and Radiation Protection Sofia - Bulgaria

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SITE DESCRIPTION

Uranium mining area "Iskra" is located in west “Stara Planina”mountain , next to the village of Katina and city Novi Iskar about 15 km north of Sofia.

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SITE DESCRIPTION

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Area "Iskra" is located in the catchment of the

river “Taina”, which is left affluent of the River Iskar.

Total area is approximately 4 km2 and long

1.2 kilometers.

Moderate continental climate, bordering the

mountain area. (There are cold winters with

average January temperatures below 0 ° C and a long and hot summers with average July temperatures around 20 °C typically).

SITE DESCRIPTION

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Precipitation in the area have a clearly

expressed maximum principal in spring - summer season (May - June) and the main minimum in winter (February)

Average annual rainfall is in the range 640 -

700 mm

The prevailing wind direction during the year

is from the west.

Area of Katina village is approximately

20.527km2 with a population of about 931 citizens

SITE DESCRIPTION

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OPERATION HISTORY

1956 - The development of the deposit began

through open-pit mining of peak “Brezy brah” Simultaneously trace the horizontal facilities in lower horizons.

1962 – Classic mining shut down due to

depletion of stocks

1982 – Reassessment of stocks was made 1985 - In situ leaching technology was

  • rganized
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1992 – Closing of the Uranium mining 2000 – Technical liquidation was completed. It

consisting of:

Above-ground facilities

Dismantling the equipments Demolishing the buildings Decontamination Depositing the radioactive waste

Underground facilities

Closing with two concrete walls

ACTUAL SITUATION

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ACTUAL SITUATION

2005 - The technical remediation was completed. It

consist of:

Stabilization and reshaping of the surface Removing of the surface water Covering in no radioactive soil layer Measuring of the gamma dose rate Calculating the thickness of the layer Covering in the soil layer

2008 - The biological remediation was completed. It

consist of:

Revegetation Growing a plants or a bushes

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2005 – The polluted water is purified with

sorption column

ACTUAL SITUATION

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Pathways of migration

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Exposure pathways

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MATERIALA AND METHODS

Sampling

water, sediment 100 m. after lake P6 water, sediment River “Taina” P7 soil Gully after SC P3 River “Iskar” Lake “Kiselo” Waste rock pile After SC Before SC Description of the area water, sediment P8 water, sediment P5 air P4 water, sediment P2 water P1 Environmental components Sampling point

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Sampling map

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Natural radionuclides Unat Ra-226, gross alpha activity Rn concentration Gamma dose rate Radiation parameter Gamma spectrometry Soil, sediment Radiochemistry water Direct measurement air Methods Environmental components

MATERIALA AND METHODS

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RESULTS – direct measurement

180 ± 20 P6 160 ± 20 P7 230 ± 30 P3 160 ± 20 200 ± 20 350 ± 40 250 ± 30 230 ± 30 Gamma dose rate [nSv/h] P8 P5 16 ± 7 P4 P2 P1 Rn concentration [Bq/m3] Sampling point

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RESULTS – soil and sediment samples

36.2 ± 2.1 35.0 ± 1.7 5.5 ± 0.8 P8 54.4 ± 4.1 35.4 ± 1.7 9.9 ± 1.6 P7 47.3 ± 3.7 38.0 ± 2.2 16.0 ± 2.8 P6 33.9 ± 2.0 165 ± 7 14.5 ± 1.8 P5 40.3 ± 3.8 235 ± 11 10.3 ± 2.0 P3 15.8 ± 3.4 122 ± 6 116 ± 8 P2

232Th

[Bq/kg]

226Ra

[Bq/kg] Unat. [mg/kg] Sampling point Activity concentration

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RESULTS – water samples

P8 P7 P6 P5 P2 P1 Sampling point ≤ 0.2 0.004 ≤ 0.02 7.62 ≤ 0.2 0.004 0.08 ± 0.02 8.16 ≤ 0.2 0.004 0.09 ± 0.02 6.80 1.74 ± 0.15 0.006 0.14 ± 0.02 2.91 7.02 ± 0.13 0.018 0.54 ± 0.07 2.64 10.44 ± 0.13 0.019 0.80 ± 0.08 2.63 Gross α [Bq/l]

226Ra

[Bq/l] Unat. [mg/l] PH Activity concentration

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Dose assessment – type of assessment (ICRP- Publication 101)

Actual impacts after emergency Emergency planning Emergency Earlier exposures Future prolonged exposures (e.g., after remediation) Existing Dose to the public from past

  • perations or compliance

with dose the dose constraint for past year Design of new facility or compliance with the dose constraint for an upcoming year Practice Retrospective Prospective TYPE OF ASSESSMENT SITUATION

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Dose assessment – type of assessment (ICRP- Publication 101)

Existing situations may require prospective assessments or retrospective assessments to determine the implications of proposed

  • actions. The assessment provides the basis

for understanding the future consequences if no actions are taken, or for understanding the dose averted if certain actions are implemented.

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Deterministic methods which involve the direct multiplication of selected point values of parameters and environmental concentrations:

screening method - very conservative assumptions

are made to estimate dose using concentrations of radionuclides at the point of discharge to the environment.

general assessment - involves populations,

pathways.

Dose assessment – type of assessment (ICRP- Publication 101)

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Model for dose assessment

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Dose assessment – without sorption column

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Dose assessment – with sorption column

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Treatment of uncertainties in dose assessment

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Conclusion

It is difficult to take a decision using only dose

assessment when the doses is low

Need of additional cost assessment on

purpose to apply ALARA

Alternative options have to be assessed