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A Brief Overview of the Radioprotection Activities in the Joint Research Centre Ispra - Italy Nina JUDGE * and Francesco D’ALBERTI ** * Medical Service.

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Presentation on theme: "A Brief Overview of the Radioprotection Activities in the Joint Research Centre Ispra - Italy Nina JUDGE * and Francesco D’ALBERTI ** * Medical Service."— Presentation transcript:

1 A Brief Overview of the Radioprotection Activities in the Joint Research Centre Ispra - Italy Nina JUDGE * and Francesco D’ALBERTI ** * Medical Service Ispra, DG ADMINISTRATION- L7, JRC - Ispra ** The Safety, Security and Radiological Protection Unit - IPSC, JRC - Ispra.

2 2 THE JRC'S MISSION To provide customer driven scientific and technical support for the conception, development, implementation and monitoring of the European Union policies

3 3 The seven JRC institutes are located in five Member States

4 4

5 5 THE JOINT RESEARCH CENTRE - ISPRA

6 6 THE RADIOPROTECTION ACTIVITIES Medical Service Ispra Capabilities Provides routine bioassay monitoring for workers on and off the site On - site Emergency decontamination facility

7 7 Analysis capabilities include: Ion Coupled Plasma -Mass Spectrometry Gamma Spectrometry Alpha spectrometry for plutonium, americium, uranium, thorium, neptunium and others Tritium analysis in bioassay samples

8 8 Fig.1 ICP-MS laboratory

9 9 Fig.2 Alpha Spectrometry laboratory with 90 counting chambers

10 10 Fig.3 Microdigest 3.6 open vessel digestion of twelve samples simultaneously

11 11 Fig.4 Electrodeposition apparatus

12 12

13 13

14 It can be concluded that these results do not show any observable concentrations of Am- 241, Pu- 238, Pu- 239,240 and U- 238 contamination in the urine samples analysed.

15 15 The Safety, Security and Radiological Protection Unit IPSC- JRC - Ispra TASKS AND ACTIVITIES Control of environmental radioactivity inside and outside the JRC Control of the workers exposed to ionising radiation Radioprotection Support to the European Union Consultancy in Radioprotection, instrument calibration and meteorological data for third parties

16 16 FACILITIES Radiochemistry laboratory(sample treatment) Radiometry laboratory( ,  and  radioactivity) On-line Data System(   and  radioactivity in airborne continuously sampled) Dosimetry Service(environment and workers’ dose assessment) Instrument Calibration Laboratory (Accredited Secondary Standards Laboratory) Whole Body Counter (internal contamination) Meteorological Observatory (pressure, temperature, humidity, solar radiation, intensity and direction of wind)

17 17 The Safety, Security and Radiological Protection Unit IPSC- JRC - Ispra INSTRUMENTS  spectrometry system (solid state detectors)  spectrometry system (solid state detectors) gross  and  system  ZnS(Ag) and GM counters) HTO system (liquid scintillator counters) environmental  radiation (plastic scintillator counters)  dose (TLD badges and reader)

18 18 MEASUREMENTS OF RADIOACTIVITY IN ENVIROMENTAL SAMPLES at The Safety, Security and Radiological Protection Unit, IPSC - JRC - Ispra airborne samples(HTO,  gross and spectr.,  gross and 90 Sr,  spectr.)~ 500/y fall-out samples(HTO,  gross and spectr.,  gross and 90 Sr,  spectr.)~ 80/y water samples(HTO,  gross,  gross and 90 Sr,  spectr.)~ 350/y soil samples(  spectr.)~ 12/y herbage samples( 90 Sr,  spectr.)~ 50/y milk samples(HTO, 90 Sr,  spectr.)~ 70/y fish samples(  spectr.)~ 10/y various samples(  spectr.)~ 50/y environment  dose rate (TLD)~ 250/y Total~ 1400/y

19 19 ISPRA DATA

20 20 ISPRA DATA

21 21 ISPRA DATA

22 22 ISPRA DATA

23 23 ISPRA DATA

24 24 ISPRA DATA

25 25 ISPRA DATA 1,00E-10 1,00E-09 1,00E-08 1,00E-07 1,00E-06 1,00E-05 1,00E-04 1961196619711976198119861991 Pu-239+240 Pu-238 239-240 Pu and 238 Pu in air 1961-1995 (Bq/m ) 3

26 26 ISPRA DATA 0,0E+00 5,0E+01 1,0E+02 1,5E+02 2,0E+02 1977198219871992 Gamma doseinside JRC 1977-1996 (nSv/h) 0,0E+00 5,0E+01 1,0E+02 1,5E+02 2,0E+02 1977198219871992 Gamma doseoutside JRC 1977-1996 (nSv/h)

27 27 ISPRA DATA The presence of low contamination in the environment around JRC and the possible doses to the population are due to the consequences of: the nuclear accident in Chernobyl the nuclear experiments performed in the atmosphere around 1960 The radioactive effluents discharged by the JRC establishment in the environment have always implied a negligible effective dose equivalent The evaluation of the data through the years must take into account the changes in the instrumentation i.e. the improvement of the minimum detectable activities.


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