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EDF RADIOACTIVE WASTE MANAGEMENT

EPRI International Low-Level Waste Conference

June 21-23, 2016

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SUMMARY

Accessibilité limitée| EDF Radioactive Waste Management | 06/2016

1. EDF NPP’S

2. RW CLASSIFICATION AND MANAGEMENT

3. FRENCH NUCLEAR WASTE ROUTES AND EDF WASTE PACKAGES

4. RADIOACTIVITY DECLARATION

5. DIFFICULTIES AND OBJECTIVES

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ELECTRICITY GENERATION BY EDF

In 2015 : 462,5 TWh (total France : 546 TWh)

Nuclear : 416,8 TWh

Consumption : 475,4 TWh

Nuclear represents 76,3 % of the electricity generation


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Waste Repository

Reactors

In operation

Dismantling

PWRs900MWe

GasCooled

Reactor1300 MWe1450MWe

Heavy Water

Reactor

FastBreed

Reactor

Gravelines

PenlyPaluel

Nogent

Flamanville Chooz

Cattenom

Fessenheim

Bugey

Chinon St-Laurent

Blayais

Golfech Tricastin

St Alban

Civaux

DampierreBelleville

Brennilis

Cruas

300 MW

Creys-Malville

Manche58 PWR reactors in operation

9 reactors undergoing dismantling(Shutdown between 1982 and 1998) CSA

CIRES

300 MW

EDF FLEET

CentracoIncineration and Melting Facility


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WASTE ZONING IN NPP

5 EDF - Radioactive Waste Management - 02/12/2013


No “universal clearance” level for RW in France=> implementation of a system with a “defence in depth” approach Facility waste zoning: conventional (CWZ) and nuclear (NWZ) Systematic waste outgoing checks Possible additional measurement upon entry on disposal

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WASTE CATEGORIZATION AND CHANNELSActivity Short –lived (<30 y) Long-lived (> 30 y)

VLLW< 100 Bq/g (Avg 10Bq/g)

VLLW disposal center (CIRES)

On site storage (safety considered for mining residue)

LLW

100 – 20 000 Bq/gLLW and ILW disposal center (CSA)

Dedicated sub-surface disposal under considerationgraphite & radium bearing

ILW20 000 – 109 Bq/g

Activated materials (NPP) : ICEDA (2018) then CIGEO

HLW> 109 Bq/g

Waste streaming from UF recycling dedicated to geological facility (CIGEO) : 2025 or later

Waste categorization <==> linked to elimination channels• No simplistic value for radionuclide activity limits• Acceptance criteria derived from repository safety cases study


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THE MAIN ACTORS

Regulatory Body (Safety Nuclear Authority)Waste management safety and Radiation protection supervision

ANDRA (National Agency for Radioactive Waste management) ANDRA’s responsibilities

• Industrial : to operate waste disposal centers• Research : to develop elimination channels for all waste• Public information : to maintain an updated inventory

Waste producers (EDF, CEA, AREVA and others) Responsibility from waste generation until its final elimination


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WASTE MANAGEMENT ORGANIZATION IN EDF

Policy for radioactive waste is defined by 3 centralizedunits in : The Nuclear Production Division The Decommissioning Division The Nuclear Fuel Division

The 3 divisions are in charge of WM strategy, processdevelopment, transportation, relations with safety authoritiesand the disposal centers operator. The waste generators (19 NPP in operation and 6 NPP

under deconstruction) in charge of the sorting,characterization and conditioning of the waste.

And technical support units (research, chemistry…).


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EDF WASTE MANAGEMENT PRINCIPLES

To assess, manage and limit the environmentalimpact of our liquid and solid radioactive waste,

To carry out global processes in order to takeadvantage of the standardization of the NPP,

Waste treatment on line and limitation of storageduration,

Quality system and waste traceability


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THE FRENCH NUCLEAR WASTE ROUTES

4 main routes for nuclear waste produced in operation: Disposal for LLW/ILW short lived ( ANDRA Centre Aube / CSA)

Disposal for VLLW (ANDRA Centre de Morvilliers / Cires)

CENTRACO plant (operated by Socodei which is EDFsubsidiary) for LLW (incineration and melting units)

AREVA La Hague reprocessing plant for spent fuel and HLW sub-surface storage (fission products glasses)

Two more expected for the long-term : Iceda , EDF conditioning and storage facility for ILW (2018)

ANDRA deep geological disposal for HLW and ILW long-livednuclides (under progress, Cigeo)


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Activity Wastes and originsVery Low Level Activity (VLLW) - Ion Exchange Resins (SGBDS)

- Maintenance Wastes (scraps, dry wastes)- Inert wastes (rubble, gravel)- Ventilation filters, iodine traps

Low Level Activity (LLW)Dose rate < 2 mGy/h

- Maintenance Wastes:. Metallic wastes, plastics, cardboard, papers, rags. Workers PPE. Oils, solvents, chemical effluents from cleanings

- Ventilation filters (GWTS, LWTS) Water circuit filters (SWTS, SGBDS)

Intermediate Level Activity (ILW) -mainly composed of short live nuclides-

- Evaporator bottom concentrates, - Sludge (sumps, tanks) - Ion Exchange Resins from the primary circuit (CVCS,

FPPS/FPCS, LWTS)- Water circuit filters (CVCS, BRS, FPPS/FPCS, SWTS)- Maintenance wastes (depending on activity measured)

Intermediate Level Long LiveActivity (ILW – LL)

- Activated core components (RCCA, ECI-fingers,…)

NPP WASTE


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CENTRACO FACILITYStarted in

1999

Incineration unit : LLW

solid and liquid

Melting unit : metallic waste


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CENTRACO FACILITYIncineration Melting

Cylindrical shields

recycled

Metallic box for air filters

and refractory

Heavy drum for ashes and

clinker

Main acceptance criteriaMass activity: < 20,000 Bq/g β/γ et < 370 Bq/g αwith an expected average of :.1,000 Bq/g for burnable wastes. 200 Bq/g for scraps1 Bq/g for α

Dose rate: < 2 mSv/hrScraps: Length : < 2 m,

Weight : < 4 t

ingots


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CIRES (VLLW DISPOSAL CENTER - ANDRA)Opened in 2003 (1rst waste package disposed the 1/10/03)

Technical concept similar to chemical hazardous waste disposal

Surface disposal embedded in clay layer

Capacity: 650 000 m3

Operation : 30 years


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VLLW DISPOSAL CENTER The main barrier against radionuclide dispersion is provided by the

geological formation being used for waste disposal. Inert waste (rubble..),common industrial waste (pipes, resins..) and

dangerous waste ( abestos, electonic materials..)

Activity 10 Bq/g (with max 100 Bq/g)


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WASTE PRODUCTION IN 2015Some figures : VLLW : Metallic, rubble : 1300 t

Resins, active carbon filters : 400 t

LLW (incineration and melting)Metallic : 231 t

Solid waste : 1975 t 85 % of total burnable solid waste

Concentrates (boron 50 g/l) : 392 t

Liquids (special operations) : 2107 t

Oil : 45 tAccessibilité limitée| EDF Radioactive Waste Management | 06/2016

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CSA (DISPOSAL CENTER LLW AND ILW) - ANDRA

BNI opened in 1992

(1rst waste package the 13/01/1992)

Capacity: 1 000 000 m3

Operational duration : 60

years


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LLW AND ILW WASTE ACCEPTANCE CRITERIA

The waste nature (nature, toxic content..) The waste forms (mechanical and containment

properties…) The specific activity limits (activity assessment..) The properties of the container (mechanical and

containment properties..) The final waste package (drop test, fire…)

The acceptance criteria to be fulfilled by the waste packagesare derived from the operational safety and long termassessments.Waste package is the first containment barrier on the multiplebarrier concept.Waste acceptance criteria concerning :


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DRUMS COMPACTION AT THE CSA

19 EDF - Radioactive Waste Management -02/12/2013


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C1 (2 m3 ) an C4 (1.23 m3 )

h = 1,300 mm d = 1,400 / 1,100 mm

Licensed in France as an IP2 container (mass activity < 10-4 A2/g)

EDF CONTAINER : C1/C4 CONCRETE CONTAINER


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RESINS AND WATER FILTERS WASTE PACKAGE

Concrete container : Lastingand confining

Concrete envelop : th = 15 cm

Shielding

Mortar


2 mobile machines in operation

In 2015 : Processing of 290 m3 IER

Conditioning of about 395 liters of IER per concrete container 2 m3

Mixing blade

IER + epoxy matrix

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WASTE PRODUCTION IN 2015

ILW• Solid wastes : 395 w.p. (790 m3)• Water filters : 1040 w. p. (1560 m3)


0

50

100

150

200

250

300

35019

8619

8719

8819

8919

9019

9119

9219

9319

9419

9519

9619

9719

9819

9920

0020

0120

0220

0320

0420

0520

0620

0720

0820

0920

1020

1120

1220

1320

1420

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LLW : • Solid waste : 1300 t

(9658 200 l drums)

• Resins : 232 m3

• Evaporator bottoms, sludge : 464 w.p. (928 m3)

Waste production after conditioning(m3/reactor)

118,9 m3/reactor

| 23Accessibilité limitée| EDF Radioactive Waste Management | 06/2016

Homogeneous waste: gamma spectrometry of wastes (IER) or samples (evaporator bottoms, oils, sludge…)

Heterogeneous waste: standard spectra available Activity content of a package arises from dose rate in contact with the

package, by using transfer functions (GBq mSv/h)

Each spectrum is periodically confirmed by gamma measurement series

Nuclides S222 (water filters)

S122 (others)

60Co 23 % 39 %

58Co 55 % 41 %

54Mn 9 % 4 %

65Zn 1 % 1 %

110mAg 11 % 11 %

125Sb - 1 %

134Cs - 1 %

137Cs 1 % 2 %

Principle: Considering the homogeneity of the

fleet (chemistry, materials…), the waste own the same original spectra

EPR is planned to get its own spectra (due to the evolution of 60Co)

RADIOACTIVITY DECLARATION : NUCLIDES EASILY MEASURABLE (GAMMA EMITTERS)

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RADIOACTIVITY DECLARATION: NUCLIDES DIFFICULT TO BE MEASURED (BETA & ALPHA EMITTERS)


Before disposal, specific nuclides in waste packages have to be declaredin accordance with limits and criteria derived from safety assessment ofthe disposal facility.

In France, for the two disposal facilities in operation, these limitsconcern 143 different nuclides (*). Most of them are DTM (β or αemitters)

EDF has implemented for 80s the scaling factor method (key nuclides :60Co and 137Cs) and now is declaring in VLLW and LILW produced duringoperation: 8 β/γ emitters (type spectra + dose rate or gamma spectroscopy on

samples or directly on packages) 3H (fixed or measured in evaporator bottoms) 18 β and ε emitters + 55Fe, 90Sr, 241Pu (β ) (all DTM) α emitters (238+239+240+241Pu, 241Am, 243+244Cm), all DTM in the case of

« serious fuel failure » (*) declaration thresholds from 10-4 to 10 Bq.g-1

example : 60Co and each α emitter : 10-1 Bq.g-1 for VLLW disposal and 10 B.g-1 for LILW disposal

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RADIOACTIVITY DECLARATION: NUCLIDES DIFFICULT TO BE MEASURED (BETA & ALPHA EMITTERS)


Type of Nuclide

Homogenous solidified waste(active ion exchangers’ resins)

Heterogeneous solidified waste(water filter cartridges)

Evaluated DTM nuclide Key nuclide Evaluated DTM nuclide Key

nuclide

CP nuclides

10Be, 14C, 36Cl, 41Ca, 55Fe, 59Ni, 63Ni, 93Mo, 93Zr, 94Nb,

108mAg, 60Co

10Be, 14C, 36Cl, 41Ca, 55Fe, 59Ni, 63Ni, 93Mo,

93Zr, 94Nb, 108mAg, 60Co

FP nuclides

79Se, 90Sr, 99Tc, 107Pd, 121mSn, 126Sn, 129I, 135Cs,

151Sm, 241Pu (β) 137Cs

79Se, 99Tc, 107Pd, 121mSn, 126Sn, 129I, 135Cs, 151Sm,

241Pu (β) 137Cs

90Sr 60Co

Alpha emitting nuclides

Total alpha emitting nuclides and 238/39/40/41Pu,

241Am, 243/44Cm60Co

Total alpha emitting nuclides and

238/39/40/41Pu, 241Am, 243/44Cm

60Co

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THE MAIN DIFFICULTIES

Waste acceptance process : Long process (until severalyears), long and complex tests for qualification of wp, newtests if changing components of package or specifications

Waste production control (resins, filters) Sorting : forbidden waste (water, greasy waste, aluminium,

batteries…), LLW and ILW resins Characterization : chemical composition and toxic content

of some waste (sludge) Activity : sample representativeness (chemical or activity

measurements), validation of scaling factors for DTM Process : not always optimized, no conditioning process for

some waste or only one route Historical waste


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MAIN OBJECTIVES To reduce waste generation (process

waste and operational waste) To seek optimization of each step of the

process To improve segregation of waste ( nature

physical , activity) To maintain quality of waste package To exchange with ANDRA, Safety

Authorities and other producers aboutdisposal requirements

To share with foreign operators (scalingfactors, process)

To find alternative channels for all thewaste especially resins and channels for« orphan » waste (electronic devices,abestos..)

27 EDF - Radioactive Waste Management - 02/12/2013


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THANKS YOU FOR YOUR ATTENTION

edf radioactive waste management - s3.amazonaws.com · bq.g-1 for vllw disposal and 10 b.g-1 for...

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