waste disposal for nuclear power plants
DESCRIPTION
Waste Disposal for nuclear power plants. A technologically solved challenge. Energy mix of Germany's electricity supply between 1960 and 2010. 100. Renewables*. 90. Oil and natural gas. 80. 70. 60. Lignite. 50. Share of electricity generation in %. 40. 30. 20. Hard coal. - PowerPoint PPT PresentationTRANSCRIPT
Waste Disposal for nuclear power plantsA technologically solved challenge
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100Renewables*
Sha
re o
f ele
ctric
ity g
ener
atio
n in
%
Oil and natural gas
Hard coal
Lignite
Nuclear power
*Hydro power, wind energy, biomass, photovoltaics, domestic waste and geothermics; practically only hydropower prior to 1990
90
80
70
60
50
40
30
20
10
0
1960 1970 1980 1990 2000 2010
Former West German States Old and newFederal States
Energy mix of Germany's electricity supply between 1960 and 2010
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19 %Oil and natural gas
23 %Nuclear
23 %Lignite
19 %Hard coal
16 %Hydro power and
other renewables
Energy mix of Germany's electricity supply from 2010
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Brunsbüttel
GreifswaldBrokdorf
KrümmelStadeUnter-weser
EmslandGorleben
RheinsbergLingen Grohnde Asse
MorslebenKonrad
Ahaus
Würgassen
Hamm-Uentrop
Duisburg
Jülich
Mülheim-Kärlich
Biblis Kahl
Grafenrheinfeld
MitterteichPhilippsburg
ObrigheimKarlsruhe
NeckarwestheimGundremmingen Isar
Niederaichbach
Nuclear power plant
Authorisation for electricity production expired in 2011according to the 13th AtG (Atomic Energy Act) amendment
Nuclear power plant shut down
Nuclear power plant completely decommissioned
Research facility with wastetreatment facility
Waste treatment facility
Central interim storage facility
Repository
1 Exploration
2 Emplacement completed
3 Construction
Nuclear power plants and their corresponding disposal facilities in Germany
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Radioactive residual materialsfrom nuclear power plants
For conventional use, recycling orremoval of released materials
Waste
Operational wastes
Spent fuel assemblies- high level- thermogenic
Other radioactive materials- low or intermediate level- non-heat-generating
Decommissioning wastes
Other radioactive materials- intermediate or low-level- non-heat-generating
Differentiation of the radioactive residual materials
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Radioactivity
heat-generatingwastes
high level
Waste designation Examples of waste Final disposal
Distribution of totalvolume of waste
intermediatelevel
lowlevel
wastes with negligible heat generation
Fission products from reprocessing
Conditioned fuel assemblies
e.g. Gorleben repository
5 % of the volumeof waste with 99 % of radioactivity
Core components
Wastes from reprocessing
Operational waste from nuclear power plantsWaste from decommissioning
Konrad repository
95 % of the volumeof waste with 1 % of radioactivity
Bq/m3
1016
1014
1012
1010
108
Classification of radioactive wastes
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Final disposal
Direct finaldisposal
Storage in the fuel poolof the nuclear power plant
Spent fuelassembliesNew fuel
assembliesNuclear power plant
Interim storage in the central interim storagefacility or in the on-site interim storage facility
ConditioningReprocessingWaste
Fuel assembly manufacture
Uranium andPlutoniumrecycling
Disposal routes for fuel assemblies in Germany
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11 billion (109) kWh
4 transprot flasks Reprocessing Fuel elements- Uranium- Plutonium
Final disposal Interim storage facility ≤ 2 casks, e.g. CASTOR® type- 1/3 high level waste
(glass canisters)- 2/3 intermediate level waste
Canisters (approx. 10 m3)
Nuclear power plant40 fuel assemblies( 21 t nuclear fuel)≅
Fuel assembly disposal:reprocessing / statistics for a pressurised water reactor per year of operation
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11 billion (109) kWh
2 casks for– transport and interim storage– e.g. CASTOR® type
Fuel assembly storage
Final disposal e.g. 4 POLLUX® disposal casks
Nuclear power plant40 fuel assemblies( 21 t nuclear fuel)≅
Fuel assembly conditioning
Fuel assembly disposal:direct final disposal; statistics for a pressurised water reactor per year of operation
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Decay storageRadioactive residual materialsaccruing in the
radiation-controlled area
Separate collection accordingto material type and
activity inventory
Direct reuse or recycling in the nuclear field possible
and economically viable?
Reuse or recycling in the nuclear field
Decontamination measures orbuffer storage are to be verified and/or
implemented if necessary
Release according to §29 StrlSchV (radiation protection ordinance)possible, economically viable?
Release
- Unrestricted release- Release for disposal- Release of scrap metal for recycling- Release of buildings for demolition- Release in the individual case procedure
Radioactive waste Conditioning Interim storage and final disposal
YES
YES
NO
NO
Disposal routes for radioactive by-products from radiation-controlled areas
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Manufacture of new productsfor nuclear fields
Melting
Final disposalin Konrad
Waste packages
Interim storage facility
Radioactive waste,e.g. slag, filters
New products,e.g. waste containers
Scrap metal
Waste packages
Controlled recycling of metals
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Radioactivity
Bq / m3
106
1014
1012
1010
108
2 m3
2 m3
2 m3
18 m3
1 m3
170 m3
2 m3
2 m3
Bead resinsFilter cartridge insertsMetal components
Evaporator concentrates
Filter concentrates and sludgesSolid waste
Bead resins
Oils
Typical operational wastes for a NPP with a PWR, by way of example annual raw wastesof a 1,300 MW plant and radioactivity spectrum
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Liquid wasteSolid wasteType of waste
Raw waste
Conditioning
Waste products
Repository cask
Metal components,rubble, etc.
Metalcomponents, insulation,etc.
Paper, plastics, fabrics, etc..
Oil Sludges Evaporatorconcentrate Filters
Ion exchanger resin conc.
Incineration Drying, dehydration, cementing
Compacting
Solid waste Compactedpellet
Salt block, granulate,powder, cement block
E.g. container,cast iron containerE.g. container
Optimised treatment methods for solid and liquid radioactive wastes from nuclear power plants
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Raw waste High-pressure compaction Incineration Incineration &high-pressure compaction
1/1to
1/5
to1/50
to1/100
Waste treatment methods for volume reduction
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Konradrepository
Annual operational wastesfrom 17 power plants withan output of 21,500 MW
3,900 m3 raw waste
11 PWR plants 6 BWR plants
1,700 m3 2,200 m3
800 m3
Waste conditioning Interim storage facility
Annual waste volume from operation of the German nuclear power plants as of 2010
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Charging system Secondaryand
afterburnerchamber
Heatrecovery
Addition of lime and
active charcoalFan
Vent stackPrimarychamber
Incineration furnace Exhaust gas cooler Bag filter I Bag filter II
Flow diagram of an incineration facility for radioactive wastes
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Shut-down nuclear power plants in GermanyPlants of the electricity supply companies
Plant Output in MWe Operating time Status
VAK Kahl 16 1960 to 1985 completely removed
KRB A Gundremmingen 250 1966 to 1977 dismantling
KWL Lingen 254 1968 to 1977 safe entombmentdismantling application made
Obrigheim 357 1968 to 2005 dismantling
Würgassen 670 1971 to 1995 dismantling
Stade 672 1972 to 2003 dismantling
Mülheim-Kärlich 1302 1986 to 1988 dismantling
Biblis A 1225 1974 to 2011
Authorisation for electricity production expired on entry into force of the 13th amendment to the Atomic Energy Act
Biblis B 1300 1976 to 2011
Brunsbüttel 806 1976 to 2011
Neckarwestheim 840 1976 to 2011
Isar 1 912 1977 to 2011
Philippsburg 1 926 1979 to 2011
Unterweser 1410 1979 to 2011
Krümmel 1402 1983 to 2011
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Shut-down nuclear power plants in GermanyPlants of the German Federation / Federal States
Plant Output in MWe Operating time Status
MZFR Karlsruhe 58 1965 to 1984 dismantling
AVR Jülich 15 1966 to 1988 dismantling
THTR Hamm-Uentrop 308 1983 to 1988 safe entombment
Rheinsberg 70 1966 to 1990 dismantling
HDR Karlstein 25 1969 to 1971 completely removed
Niederaichbach 106 1972 to 1974 completely removed
Greifswald 1 440 1973 to 1990 dismantling
Greifswald 2 440 1974 to 1990 dismantling
Greifswald 3 440 1978 to 1990 dismantling
Greifswald 4 440 1979 to 1990 dismantling
Greifswald 5 440 trial operation1990 dismantling
KNK II Karlsruhe 20 1977 to 1991 dismantling
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Total mass of the radiation-controlled area(PWR reference power plant)
156,500
Distribution of the accrued masses during dismantling of the radiation-controlled area of a PWR (indications in t)
Concrete and reinforcement
Plant components
Radioactive waste(concrete/reinforcement)
Material for harmlessrecycling
Waste for conventionaldisposal
Radioactive waste(plant components)
Radioactive waste(secondary waste, e.g. from decontamination)
For final disposal
For harmlessrecycling
For dumping
For final disposal
For final disposal
600
9,800
700
3,00013,500
500
For freerecycling 143,000
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Work sequence plansapplication to
Treatment of radioactive wastes with step-by-step accountsconcerning interim storage and final disposal
Preliminary testingProcedure qualification
Work sequence plansrelease
Accompanying control
Documentation
Test report
Release
Supervisory authority BfS
Interim storage facility Repository
Preparationfor conditioning
Conditioning
Interim storage/final disposal
Responsibility
Waste producer
RepresentativeExpert
BfS/supervisory authority
RepresentativeExpert
Waste producer
RepresentativeExpert
BfS/supervisory authority
Interim storage/final disposal
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Responsible institutions in final disposal of radioactive wastes in Germany
BMUFederal Ministry for the Environment, Nature Conservation and Nuclear Safety
RSKReactor safety commission
SSKRadiation protection commission
ESKDisposal commission
BMWiFederal Ministry of Economicsand Technology
BfSFederal Office for Radiation Protection
BGRFederal Institute for Geosciences and Natural Resources
DBEDeutsche Gesellschaft zum Bau und Betrieb von Endlagern für Abfallstoffe mbH
RSK/SSK/ESK consultancy
Federal State Auth.Planning approval
Mining authoritiesPlanning approvals DBE
Constructor and operator
BfSResponsible for construction
and operation, applicant
BMUAdministrative and
technical supervision
BMWiAdministrative and
technical supervision
BGR
Gorleben projectKonrad repository
Waste producer
Necessary expenditureOrdinance on Advance Payments for the Establishment of Federal Facilities for Safe Custody and Final Storage for Radioactive Wastes
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Responsibilities for disposal of radioactive wastes
Nuclear power plant operator
Duty to surrender
German Federation
Development, operation and decommissioning of the power plants
Development of suitable methods for treating waste and fuel assemblies
Performing reprocessing/conditioning Interim storage
Financing of final disposal
Final disposal
- Exploration - Construction - Operation - Decommissioning
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Structure of a repository for radioactive wastes in a salt formation
Overburden
Salt dome
Repository containers(fuel assembly casks)
Depth approx. 800 m
Depth approx. 1,100 m
Repository containers (canisters)
Tunnel
Bore holes