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TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE

IAEA, VIENNA, 25-28 NOV. 2013

CHARACTERIZATION OF LARGE VOLUME OF WASTE, LARGE COMPONENTS AND SOILS

Lucien Pillette-Cousin AREVA TA

Contents

General considerations regarding waste characteristics in case of nuclear accident

Experience from characterization of decommissioning waste

Experience from characterization of large components/waste packages

Characterization of contaminated soils and sites

Example of characterization applied to legacy waste: remediation of the Gremikha site

Nucléaire et renouvelables : Concluding remarks deux énergies complémentaires pour un mix avec moins de CO , 2 économique et fiable.

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Waste characteristics in case of nuclear accident General considerations (1)

Factors affecting quantity of waste from clean-up are (not limited to):  Large amounts of various physical nature  Extent, depth and nature of  Characteristic of environment affected (urban, forest, agriculture etc.)  Meteorological conditions  Decision on handling the affected area e.g. stabilization, interdiction or clean-up  Clean-up methods  Clean-up criteria applied

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Waste characteristics in case of nuclear accident General considerations (2)

 Facility design

 Accident scenario

 Dismantling strategy

 Selective deposition of

 Access to contaminated site and damaged facilities

 High background conditions for in-situ radiological characterization

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Characterization methods for D&D waste Non destructive  Dose rate and dose rate conversion method

 Gamma spectrometry (even underwater)

Hot spots, fuel fragments)

 Coupling of gamma camera and dose rate measurement

 Coupling of gamma spectrometry and measurement: passive (active)

Sampling and radiochemical analysis  For determination of scaling factors (correlation factors) for difficult to measure : pure beta, alpha nuclides (to be used carefully)

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Sampling by drilling instead of coring: the TruPro® methodology

Principle:  to collect all drilled material as a unique representative sample.  Drilling less invasive than coring, ~ 12 mm hole as opposed to 25–50 mm hole for coring - time to obtain each sample is lower (hours  min.)  Samples are smaller  homogenization easier and radioanalytical measurements faster  Applicable to slabs, walls, , , refractory block, , sand, dry soils

Quicker feedback on contaminated areas, reduction of exposure for workers, time saving for the project.

Good experience feedback at Brennilis NPP (France) on reinforced concrete through layers of 10 cm to 2.5 meters thickness, with 3 x 50 cm incremental samples

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Example of methodology for non destructive characterization of D&D waste (simple scene)

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Example of methodology for non destructive characterization of D&D waste: complex geometry modelling

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Field Dose Rate Measurements

 Well known and easy method for field measurements

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Radiological characterization of large components

In situ gamma spectrometry measurements of large size NPP components  Steam generators (before and after decontamination)  Vessel lids (e.g. EdF, France)  Ground prototype of nuclear submarine (vessel, steam generator)

Gamma spectrometry under Sampling for correlation factors pure beta: Ni-63, Nb-94, etc.. the lid (Co-60, Cs-137)

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Use of In-Situ gamma spectrometry

Verification of thermal exchanger (top left),

of raw waste (top right), in collimated geometry

and measurement of contamination in a room in open geometry (left)

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Use of In-Situ gamma spectrometry

Characterization of the pool of Triton research reactor (CEA, France) before cleanup and decommissioning (height 9m)

In-situ gamma spectrometry accomodates many characterization geometries / configurations as it is usually the case for nuclear accident

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Comparison of detectors for gamma spectrometry

Room Θ

With collimation / filtration

/ dose rate

Liquid N2 Θ

= f(time of characterization Room Θ after accident) Good compromise

Choice would also depends on time after accident and decay of very short lived radionuclides

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Radiological characterization of large size waste packages

Big-bags 1 to 2 m3 1 to 5 m3 concrete or metal containers ISO containers

Scintillation (NaI, LaBR3) or germanium detector Main concern: modelling and associated uncertainty:  Distribution of activity inside the waste package  Distribution of waste matrix and density inside waste package

3m3 container: assay in 30 minutes 0.01 Bq/g typical detection limits for Co-60

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Radiological characterization of large size waste packages Measurement of ISO container with ISOCS system (for verification of waste clearance) at Dukovany NPP (Czech republic)

 Applicable to VLLW, LLW, ILW

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Radiological characterization of large size waste packages Many data processing systems developed for characterization of large size items, for activity localization and improvement of modelling  ISOCS®, LABSOCS®  Mercurad ®  Particle Swarm Imaging (PSIM)  MCNP calculations

 Radball ®: suitable for use in hotcells, gloveboxes or enclosed areas of high : used at , proposed for Fukushima cleanup

Based on absorption of gamma radiation on a photographic film inside the ball

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Radiological characterization of large size D&D waste packages: Neutron Measurements Non destructive characterization of Pu / U content

Usually not needed for D&D waste if fuel non damaged (used for D&D of reprocessing plants)

Useful in case of severe accident with fuel damaged, e.g. A1 (Slovakia), Chernobyl, Fukushima, for determination of alpha content in waste, coupled with ϫ spectrometry (Cs-137, Pa-234m)

Result as mass of equivalent Pu-240 - Alpha isotopy taken from fuel characteristics with decay/evolution time since accident

Performances in accordance with waste acceptance criteria of the disposal facility (e.g. Vektor characterization facility – ϫ spectrometry not enough to verify compliance of waste from with WAC)

Scaling factor method for pure beta emitters

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Radiological characterization of large size D&D waste packages: neutron measurements Example: WCAS - Waste Crate Assay System

Passive neutron multiplicity coincidence counting

High resolution isotopic gamma-ray analysis

box size up to 1660 L (1.4 x 1.4 x 1.2 m)

18% efficiency for fission

MDAs of less than 6 mg Pu-240

Evolution: adaptation of homeland security portal (detection of fuel fragments)

Example: Euritrack system (under assessment)

? Development of portable neutron assay systems

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Use of gamma camera

Acquisition Image treatment

DR (662 keV) 10 mGy/h 8.9 mGy/h

7.8 mGy/h

6.6 mGy/h

5.5 mGy/h

4.4 mGy/h

3.3 mGy/h

2.1 mGy/h

1 mGy/h

visible Dose Image rate Mode Raw levels 6270.97

3541.25

gamm Brut gamma a image Image

measurements from distance • very little manual operation Superimposition of visible • “direct” interpretation of measurements and gamma image

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Use of gamma camera

Detection of hot sptots / activity concentrations Used to improve modelling (coupling with gamma spectrometry) Planning of interventions

Examples of use of gamma camera for detection of hot spots on tanks containing liquid

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 In addition: use of indoor robots

Main objective: and security of the operators Operated owing to cameras, microphones, lights, and radiation sensors

May be equipped with dose rate probes, and even gamma spectrometry probes and gamma-camera Very radiation resistant (hardened up to 10 kGy), cable of 350 m, Wifi under development for use in reactor building (too thick concrete shielding)

Example left below: EOLE (INTRA Group, France), 1 meter lenght, 70 cm width, right picture: Russian MRK type robot (Baumann Institute, Moscow)

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Site characterization before cleanup

First objective: identify hot spots, fuel fragments or pieces of activated material, to secure the area for the workers, plan cleanup work, etc.

Helicopter survey (gamma spectrometry)

Field characterization  Dose rate measurement (Radball)  In-situ gamma spectrometry

 Portable devices  Mobile laboratories

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013

Site characterization before cleanup Helicopter survey Example: HELINUC (INTRA Group, France)

On board gamma detector in a box under the Helicopter

Silmultaneous acquisition of ϫ spectrum and Helicopter position

GeHP GeHP counting time: Radionuclides NaI detector counting time: 2s 60s Cs-137 (kBq/m²) 1 6,5 0,5 Minimum Detectable Activities Eu-154 (kBq/m²) 2 10 1 K-40 (Bq/kg) 30 620 10 U-238 (Bq/kg) 10 260 20 Th-232 (Bq/kg) 3 130 13

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Helicopter survey of woods and roofs New AREVA development for Fukushima area

Unmanned helicopter equipped with automatic geolocalized measurement device  REX from Chernobyl  Helicopter size  Low elevations Detection technology  NaI probe with specific collimator  GPS Currently under qualification in

Expected mapping results Cs-137 Source

Unmanned helicopter during tests in Japan

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 In-Situ gamma spectrometry of soils

Soil measurements at Chernobyl site

Characterization of soil contaminated by NORM in Paris area

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Characterization of soils: use of laboratory vehicle: LAMAS (CEA, France)

Weather measurements Atmospheric measurements Wind vane, anemometer, Monitoring of radiological Beacons to measure temperature sensor, pluviometer, incidents and dose rate relative humidity Wind scattering Gas and aerosols activity Differential GPS measurements with submetric accuracy Centralization of the measures in the front cabin of the vehicle

In situ Gamma spectrometry Data processing through geostatistics

Samples treatment Map making Optimization of the Alpha Measurement with Perals sampling plan ‘liquid scintillation’ system Diffusion gradients

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 26 Mobile laboratory for soil/site characterization: alpha and Sr-90 measurement on samples Chemical preparation of samples

Laboratory for sample preparation, alpha measurement (U, Pu) and Sr-90: liquid scintillation counting (PERALS)

Protocols of extraction (alpha totals, U+Pu, U or Pu), for sand or ground, detection limits < 1 Bq/kg within < 24 hours. Time needed for extraction:………………………………………….5 h Counting time:…………………………………………………………8 h

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Mobile laboratories for site characterization

Mobile labs Accomodate many work conditions

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Vehicle for radiological mapping: VEGAS

Measuring devices : GPS - Gamma spectrometry GeHP, 30 % effectiveness. - NaI detector (2.4 L crystal). - Two DSP (plastic scintillation detectors) of 0,5 m² 5 cm thick

DSP

Performances at 2.5 km/h :

- Able to detect an activity >70 Bq/kg (137Cs) for 1m² soil over a thickness of 5cm. - Able to detect an activity >0,37Bq/cm² (137Cs) - Able to detect a contaminated spot (137Cs) of 3800 Bq. NaI GeHP - Exhaustive measure of 0.5 ha/h.

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Monitoring of Roads Contamination AREVA recent development for Fukushima

To be used for ground areas such as roads, playgrounds, school yards, sports areas, parks, etc. Japanese Agricultural tractor with trailer  Hydraulic dampers against bumps and vibrations  Painting device marks contamination above threshold automatically

Detection technology used:  1m large Plastic scintillation for Contamination.  GM for dose rate measurement  GPS

Field Monitoring Vehicle during final tests in Minami-soma

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 In addition: use of outdoor robotic means

Outdoor robots are larger and faster than indoor robots

Can be radio-guided up to 5 km distance

Radiation hardened (less than indoor robots), resist to few tens of Gy

Equipped with manipulator(s), they can perform:  Radioactivity measurements  Samplings  Recover active fragments  Etc.

From INTRA Group (France)

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Geophysics investigation for sampling

Confirm the position of drill holes by checking the absence of metallic parts or underground network near the drill holes.

Drillings with auger or Geoprobe Depends on the field, maximal depth: 2m Simple and relatively cheap anomaly Unsuitable for chemical measures Unsuitable for containment

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Characterization of contaminated soils and sites: Use of geostatistics

Geostatistics: integration of the phenomenon spatial continuity Main tool of geostatistics: the variogram => describes the variability between 2 points  on average, the difference between two CLOSE measures is LOW  on average, the difference between two DISTANT measures is HIGH

The way the variogram increases with distance is linked to the phenomenon spatial variability

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Geostatistics : basics

Known Data: Measurements

Data analysis

Kriging 3D Histogram

2D Interpolation 3D Interpolation (initial cartography) Experimental variogram and model (with drillings)

34

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Use of geostatistics

Interpolation Map Uncertainty Map

High variability

Uncertainty Map points out areas where there is a lack of measures or where variability is important.

98% 77% 0% 0%

May provide a risk map: Probability of 53% 10% exceeding a given activity level 46% 100% 62%

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 35 Soil sorting unit AREVA development for Fukushima Millions of tons of soil will have to be processed  REX from Chernobyl accident  Contamination stays within a depth 5~10 cm  Contamination concentrates on localized “leopard spots”:  more than half of the suspected soil is not contaminated  Measurement of soil with plastic scintillator panels

Automated high-throughput sorting of soil  100 t/h  Detection limit < 100 Bq/kg  Mobile unit in container Feeding Output conveyors

Detectors

Testing in France before shipment to Sorting hopper the Japanese demonstration site

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Underwater measurement device AREVA development for Fukushima

ROV (Remotely Operated underwater vehicle) for lake beds inspection equipped with gamma spectrometry  Capable to operate down to 200 m  Measurement of sediments contamination Detection technologies

 LaBr3 probe with countermeasures to handle water shielding issue  Ultra Sound Baseline underwater Localization (USBL) linked to main boat and GPS aboard

3D mapping of lakes with geolocalized contamination Testing of submarine unit in data France before shipment to JAEA

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 Example of characterization applied to Legacy waste:

Characterization for the remediation of the Gremikha site

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 The Gremikha Coastal Maintenance Base

Andreeva Bay Two former Soviet submarine bases in North-West Russia Andreeva Bay Gremikha

In the Frame of the G8 Global Partnership Against the Spread of Weapons and Materials of Mass Destruction, France decided to help Russian Federationfor funding and providing technical assistance and equipment for remediation of the Gremikha base.

CEA was leading the project assisted by AREVA

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 The Gremikha Coastal Maintenance Base Spent Pd-Bi cooled cores

Spent nuclear VVR fuel in open air pad and in pits in building 1 Liquid radwaste (L-ILW) in underground tanks

Solid radwaste (L-ILW, HLW) In building 19

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 The Gremikha Remediation Project First step: radiological characterization of the site (soil, water basin), buildings and objects (spent fuel assemblies, liquid and solid waste) Dose rate measurements and cartography

 Cesium 137 90 Dose rate

Dose rate measurements and cartographies around the open air spent fuel storage area

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 The Gremikha Remediation Project

Radiological characterization of the open air spent fuel storage area

Dose rate measurements and cartography of the open air spent fuel storage area

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 The Gremikha Remediation Project 2D and 3D modeling of site contamination, water basin contamination

Soil contamination

water basin

3D modelling: better understanding of contamination spreading phenomena and its composition

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 The Gremikha Remediation Project

Characterization of containers with spent fuel / HLW: external dose rate, for defining intervention conditions  use of robots

Dose rate measurement Dose rate measurement on a ‘sarcophagus’ containing HLW In the spent fuel storage open air area (control rod) fragments

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 The Gremikha Remediation Project

Characterization of casks with spent fuel / HLW: surface contamination, soil sampling, fuel fragment recovery for improving further intervention conditions  use of robots

Soil sampling

Surface contamination of casks containing spent fuel and HLW

Sampling of liquid waste in casks

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 The Gremikha Remediation Project

Characterization of hots spots on casks containing spent fuel and high level waste using the gamma camera on a mast from 5 to 20 m height.

Site : vishka 10 v Date : 27/07/2006 Scene : Heure : 12:14:37

Coups

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File : D:\L2ma\Gremikha\Mesures_aout06\Cartogam\10-6.scn [Image composite] Acquisition : Mode = FAIBLE COMPTAGE[28398c], 15min0sec480 (22512*0sec40), gain 9.99, jeudi 27 juillet, 2006, 12h14, Analysis : Fond : 0.0372, Max : 0.274, Contraste :86.40%, S/B :0.962, , , Fond, Débit de Dose (660 keV), 0 Gy/h Processing : seuil automatique (0.5),

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 The Gremikha Remediation Project

Example of characterization of hots spots on casks containing spent fuel and high level waste using gamma camera at ground level.

Gamma camera view of the open air spent fuel storage area

Hot spot detected on concrete container: characterization before its handling and further dismantling

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 The Gremikha Remediation Project

Characterization of casks with spent fuel / HLW: in-situ gamma spectrometry (ISOCS)

a b

Fig. 3. γ-spectrometer ISOCS with the -protected Ge detector during the measurements on the SRWSA: a – directed to the Bet4 container (the view from the SRWSA). b – directed down for the soil activity measurements (the view from the entrance).

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 The Gremikha Remediation Project

Intervention for recovery of a spent fuel fragment  Localization by dose rate measurement and gamma gamera  Recovery by means of robot  Fragment put into an empty shielded cask

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 The Gremikha Remediation Project

Open air storage for spent fuel: cleanup of the working zone  After removal of hot spots (fuel assembly fragment, control rods, etc  before removal of the spent fuel casks

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013 CONCLUDING REMARKS (1)

A lot of experience feedback exists worldwide regarding characterization of:  Waste from D&D waste activities  Legacy waste  Chernobyl accident  At a lesser extent (in my opinion) NORM/TENORM waste

Some techniques / domains are or become mature for characterization purposes in case of nuclear accident:  In-situ gamma spectrometry  Gamma camera and coupling with dose rate measurement and gamma spectrometry  Mobile laboratories  Indoor and outdoor robotic means and remote controlled systems  data processing: imaging, cartography for optimization of work, decision making

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013

CONCLUDING REMARKS (2)

With respect to safety of long term disposal of waste generated by a nuclear accident, efforts to be put on:

 Non destructive characterization of alpha content of waste such as soils, wood, plant residues, concrete rubble, etc.:  portable / mobile neutron measurement systems

 Address issue of long lived beta isotopes: no NDT techniques: only scaling factor method seems applicable today: method to be rended more reliable

 Improvement of techniques/tools making sampling easier and more robust

 Large size waste package and nuclear components (presently ramping up)

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013

THANK YOU FOR YOUR ATTENTION

TECHNICAL MEETING ON THE DISPOSAL OF LARGE VOLUME OF RADIOACTIVE WASTE, IAEA, VIENNA, 25-28 NOV. 2013