Transcript Folie 1

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
Share of electricity generation in %
70
60
Lignite
50
40
30
20
Hard coal
Nuclear power
10
Old and new
Federal States
Former West German States
0
1960
1970
1980
1990
2000
*Hydro power, wind energy, biomass, photovoltaics, domestic waste and geothermics; practically only hydropower prior to 1990
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2010
Energy mix of Germany's electricity supply from 2010
19 %
Oil and natural gas
23 %
Nuclear
16 %
Hydro power and
other renewables
23 %
Lignite
19 %
Hard coal
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Nuclear power plants and their
corresponding disposal facilities in Germany
Brunsbüttel
Brokdorf
Unterweser
Krümmel
Stade
Greifswald
Gorleben
Emsland
Lingen
Rheinsberg
Grohnde Asse
Ahaus
Morsleben
Konrad
Würgassen
Hamm-Uentrop
Nuclear power plant
Authorisation for electricity production expired in 2011
according to the 13th AtG (Atomic Energy Act) amendment
Nuclear power plant shut down
Nuclear power plant completely decommissioned
Duisburg
Jülich
MülheimKärlich
Grafenrheinfeld
Biblis Kahl
Mitterteich
Research facility with waste
treatment facility
Philippsburg
Waste treatment facility
Central interim storage facility
Repository
1
Exploration
2
Emplacement completed
3
Construction
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Obrigheim
Karlsruhe
Gundremmingen
Isar
Neckarwestheim
Niederaichbach
Differentiation of the radioactive residual materials
Radioactive residual materials
from nuclear power plants
Waste
For conventional use, recycling or
removal of released materials
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
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Classification of radioactive wastes
Radioactivity
Waste designation
Examples of waste
Bq/m3
Final disposal
Distribution of total
volume of waste
1016
high level
heat-generating
wastes
1014
Fission products from
reprocessing
Conditioned fuel
assemblies
intermediate
level
e.g. Gorleben repository
5 % of the volume
of waste with
99 % of radioactivity
wastes with
negligible
heat generation
1012
Core components
1010
low
level
108
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Wastes from
reprocessing
Operational waste from
nuclear power plants
Waste from
decommissioning
Konrad repository
95 % of the volume
of waste with 1 % of
radioactivity
Disposal routes for fuel assemblies in Germany
Spent fuel
assemblies
New fuel
assemblies
Storage in the fuel pool
of the nuclear power plant
Nuclear power plant
Uranium and
Plutonium
recycling
Direct final
disposal
Fuel assembly manufacture
Interim storage in the central interim storage
facility or in the on-site interim storage facility
Waste
Reprocessing
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Conditioning
Final disposal
Fuel assembly disposal:
reprocessing / statistics for a pressurised water reactor per year of operation
11 billion (109) kWh
Nuclear power plant
40 fuel assemblies
(≅ 21 t nuclear fuel)
4 transprot flasks
Reprocessing
Fuel elements
- Uranium
- Plutonium
Canisters
(approx. 10 m3)
Final disposal
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Interim storage facility
≤ 2 casks, e.g. CASTOR® type
- 1/3 high level waste
(glass canisters)
- 2/3 intermediate level waste
Fuel assembly disposal:
direct final disposal; statistics for a pressurised water reactor per year of operation
11 billion (109) kWh
Nuclear power plant
40 fuel assemblies
(≅ 21 t nuclear fuel)
Final disposal
2 casks for
– transport and interim storage
– e.g. CASTOR® type
e.g. 4 POLLUX® disposal casks
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Fuel assembly storage
Fuel assembly conditioning
Disposal routes for radioactive by-products from radiation-controlled areas
Radioactive residual materials
accruing in the
radiation-controlled area
Decay storage
Separate collection according
to material type and
activity inventory
Direct reuse or recycling in the
nuclear field possible
and economically viable?
YES
Reuse or recycling
in the nuclear field
Decontamination measures or
buffer storage are to be verified and/or
implemented if necessary
NO
Release according to §29 StrlSchV
(radiation protection ordinance)
possible, economically viable?
YES
Release
- Unrestricted release
- Release for disposal
- Release of scrap metal for recycling
- Release of buildings for demolition
- Release in the individual case procedure
NO
Radioactive waste
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Conditioning
Interim storage and final disposal
Controlled recycling of metals
Scrap metal
Melting
Radioactive waste,
e.g. slag, filters
New products,
e.g. waste containers
Manufacture of new products
for nuclear fields
Waste packages
Waste packages
Final disposal
in Konrad
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Interim storage facility
Typical operational wastes for a NPP with a PWR, by way of example annual raw wastes
of a 1,300 MW plant and radioactivity spectrum
Radioactivity
Bq / m3
1014
1012
1010
2 m3
2 m3
2 m3
Bead resins
Filter cartridge inserts
Metal components
18 m3
Evaporator concentrates
1 m3
170 m3
Filter concentrates and sludges
Solid waste
2 m3
Bead resins
2 m3
Oils
108
106
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Optimised treatment methods for solid and liquid radioactive wastes from nuclear power plants
Type of waste
Raw waste
Solid waste
Metal
components,
rubble, etc.
Metal
components,
insulation,etc.
Liquid waste
Paper,
plastics,
fabrics, etc..
Oil
Incineration
Sludges
Evaporator
concentrate
Filters
Ion
exchanger
resin conc.
Drying, dehydration, cementing
Conditioning
Compacting
Waste products
Repository cask
Solid waste
Compacted
pellet
E.g. container
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Salt block, granulate,
powder, cement block
E.g. container,
cast iron container
Waste treatment methods for volume reduction
1/1
to
1/5
Raw waste
High-pressure compaction
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to
1/50
Incineration
to
1/100
Incineration &
high-pressure compaction
Annual waste volume from operation of the German nuclear power plants as of 2010
11 PWR plants
Annual operational wastes
from 17 power plants with
an output of 21,500 MW
6 BWR plants
3,900 m3 raw waste
2,200 m3
1,700 m3
800 m3
Waste conditioning
Interim storage facility
Konrad
repository
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Flow diagram of an incineration facility for radioactive wastes
Charging system
Secondary
and
afterburner
chamber
Heat
recovery
Addition of
lime and
active charcoal
Fan
Vent stack
Primary
chamber
Incineration furnace Exhaust gas cooler
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Bag filter I
Bag filter II
Shut-down nuclear power plants in Germany
Plants of the electricity supply companies
Plant
Output in MWe
Operating time
VAK Kahl
16
1960 to 1985
completely removed
KRB A Gundremmingen
250
1966 to 1977
dismantling
KWL Lingen
254
1968 to 1977
safe entombment
dismantling 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
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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Status
Authorisation for electricity
production expired on entry
into force of the 13th
amendment to the Atomic
Energy Act
Shut-down nuclear power plants in Germany
Plants of the German Federation / Federal States
Plant
Output in MWe
Operating time
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 operation
1990
dismantling
KNK II Karlsruhe
20
1977 to 1991
dismantling
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Status
Distribution of the accrued masses during dismantling of the radiation-controlled area of a PWR
(indications in t)
Total mass of the radiation-controlled area
(PWR reference power plant)
156,500
600
For final disposal
Concrete and reinforcement
Plant components
For free
recycling
Radioactive waste
(concrete/reinforcement)
143,000
9,800
For harmless
recycling
Material for harmless
recycling
Waste for conventional
disposal
700
3,000
13,500
500
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For dumping
Radioactive waste
(plant components)
For final disposal
Radioactive waste
(secondary waste,
e.g. from decontamination)
For final disposal
Treatment of radioactive wastes with step-by-step accounts
concerning interim storage and final disposal
Responsibility
Work sequence plans
application to
Supervisory authority
Waste producer
BfS
Representative
Expert
Preliminary testing
Procedure qualification
Preparation
for conditioning
BfS/supervisory authority
Work sequence plans
release
Accompanying control
Representative
Expert
Documentation
Waste producer
Test report
Representative
Expert
Conditioning
Interim storage/
final disposal
BfS/supervisory authority
Release
Interim storage facility
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Repository
Interim storage/
final disposal
Responsible institutions in final disposal of radioactive wastes in Germany
RSK/SSK/ESK
consultancy
BMU
Administrative and
technical supervision
BMWi
Administrative and
technical supervision
BMU
Federal Ministry for the
Environment, Nature
Conservation and Nuclear Safety
RSK
Reactor safety commission
Federal State Auth.
Planning approval
Mining authorities
Planning approvals
BfS
Responsible for construction
and operation, applicant
BGR
SSK
Radiation protection commission
ESK
Disposal commission
DBE
Constructor and operator
Konrad repository
BMWi
Federal Ministry of Economics
and Technology
Gorleben project
Necessary expenditure
Ordinance on Advance Payments for the Establishment
of Federal Facilities for Safe Custody and Final Storage
for Radioactive Wastes
Waste producer
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BfS
Federal Office for Radiation
Protection
BGR
Federal Institute for Geosciences
and Natural Resources
DBE
Deutsche Gesellschaft zum Bau
und Betrieb von Endlagern für
Abfallstoffe mbH
Responsibilities for disposal of radioactive wastes
Nuclear power plant operator
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
Duty to surrender
Final disposal
German Federation
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- Exploration
- Construction
- Operation
- Decommissioning
Structure of a repository for radioactive wastes in a salt formation
Overburden
Salt dome
Tunnel
Repository containers
(fuel assembly casks)
Bore holes
Depth approx. 800 m
Repository containers (canisters)
Depth approx. 1,100 m
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