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EDF RADIOACTIVE WASTE MANAGEMENT
EPRI International Low-Level Waste Conference
June 21-23, 2016
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SUMMARY
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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
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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
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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
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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)
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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
15
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
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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)
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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)
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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..)
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