management of radioactive wastes - upcoming events » …€¦ · a hard rock : limestone, granite...

IEEE PES Workshop 29 January 2009

Management of Radioactive WastesAn overview mainly based on experiences in Switzerland

Piet Zuidema amp Lawrence JohnsonScience amp TechnologyNagra ndash National Cooperative for the Disposal of Radioactive Waste Switzerland

IEEE_Waste Management_Zuidema_2901092 29012009Zu

Nuclear Power in Switzerland5 Nuclear Power Plants (3220 MWe)KKL Leibstadt (1984) 1165 MWeKKB-I Beznau (1969) 365 MWeKKB-II Beznau (1971) 365 MWeKKG Goesgen (1979) 970 MWeKKM Muehleberg (1971) 355 MWe

0 100 200 300 km


Electricity production and consumption

Hydro (Rivers)

Hydro (Reservoirs)

Convential thermal

Nuclear

Consumption

Origin of Swisselectricity40 nuclear60 hydroelectric



Nuclear power plants in the world

Source Argonne National Laboratory International Nuclear Safety Center (INSC)


Importance of nuclear power

Source IAEA PRIS


Some general remarks Nuclear energy plays an important role in many countries Nuclear power generates small amounts of wastes

- Spent fuel ~ 20 tU GWea (CH 20 g persona)- Waste from operation ~ 50 m3 GWea (CH 05 dl persona)- Waste from dismantling ~ 9000 m3 GWe (CH 10 l person)- pm household waste ~ 2000 kg persona (CH)

However these wastes require careful management For long-lived wastes as an end-point only disposal in deep

geological layers can provide the necessary safety Therefore deep geological repositories are being developed in

many countries

1) pm considerable amounts of wastes come also from other sources (Switzerland (until 2050) waste from dismantling research facilities (incl reserves) ~ 23000 m3 operational waste from medicine research industry ~ 5000 m3)


Swiss waste management concept

Spent Fuel (SF) vitrified high level waste (HLW) HLW repository Long-lived intermediate waste (ILW) HLW repository (co-disposal) Low and intermediate waste (LILW) LILW repository


Waste management the topics The wastes

- Minimisation of wastes (incl fuel cycle)- Treatment (conditioning packaging)- Characterisation inventory (incl future wastes planning)

Interim storage- Until repositories are available- Cooling of heat-producing wastes (SF vitrified HLW)

Repositories- Overall objective passive safety for the times needed (longevity

of wastes)- Importance of geology (essential for passive safety for long time

scales stability)- Disposal concept more than one repository (waste allocation)

hellip and the corresponding transportation amp handling


Waste management the topics The wastes ( routine practice)








Fuel Cycle the possibilities (OECDNEA 2002)

Not all possibilities are used today Direct Disposal S SF today

also B CH D USA (amp UK F) Reprocessing amp Use of PuU as

MOX B CH D F Japan Option to use Pu in fast breeders

F Japan India Option to use alternative energy

systems (ADS hellip) F J Thus (in principle)

- Differences in waste form- Differences in waste toxicities- Differences in time of waste arisings- Importance of interim storage- But in all cases there is a need for

deep geological disposal




Interim storage ( routine practice)- Until repositories are available- Cooling of heat-producing wastes (SF vitrified HLW)






Today interim storage

interim storage of low- and intermediate level wastes

interim storage of spent fuelhigh-level waste in Castor-type canisters (ZWILAG)


Interim storage Netherlands (for 100 years)


Interim storage for even longer times (gt 300 years)

Storage shaftsSF or glass canister without biological shielding

ventilation gallery (air return)

Ventilation gallery (input air)

river

Handling gallery

functional layoutHillside configuration horizontal designhard rock limestone graniteAir e

xhau

st

Air inle

t

Watertable level

Drainage drift dewatering






of wastes)- Disposal concept more than one repository (waste allocation)- For long-lived waste Importance of geology (essential for

passive safety for long time scales stability)



Waste management concept different repositoriesWastes with differing properties allow for different repositories (differences in the required barrier properties incl geology)


Radiotoxicity (total inventory Switzerland)

HAA Spent Fuel vitrified HLW ATA long-lived ILW SMA LILWFor comparison radiotoxicity of natural materials (volume total volume of wastes)


Disposal concept Switzerland

Repository for low- amp intermediate level waste (LILW)

Repository for high-level (SFHLW) and long-lived intermediate level waste (ILW)

Two sites different waste categories at one site (co-disposal)


Disposal concept Sweden

(amp SFL)

Two sites possibility for different waste categories at one site (co-disposal)


Disposal concept France


France repository for HLW amp ILW (Dossier Argile)


France Repository for VLLW (Morvilliers)




Geological repository (SFHLWILW)

Ramp

Disposal tunnelsSF HLW

Shaft

Canister

Disposal tunnel withbentonite backfill

Host rock(Opalinus Clay)

Disposal tunnelILW


Layout for SFHLWILW - Repository


Waste acceptance facilities (NTB 02-02)

1 Administrationsgebaumlude2 Betriebsgebaumlude3 Luumlftungsgebaumlude4 Geraumlteschleuse

5 Konditionier- und Verpackungsanlage BEHAA6 Bahnzufahrt7 Strassenzufahrt8 Zugangstunnel Rampe (uumlberdeckt)


Engineered and geological barriers (SFHLW)

Host rock

RepositoryDisposal Canisters

Disposal tunnels with bentonite backfill

Geosphere


Radioactive decay of 1 t of spent fuelRadiotoxicity of 1 t of Swiss spent fuel and 8 t of natural U


RTI of 1 t of Swiss spent fuel and 8 t of natural U

After 1 million years no unacceptable situation also for repository system with degraded barriers


Predictability of a geological disposal system

Ecological change

Geological changeClimatic change

Individual habitsHuman activities

100

10rsquo000

1rsquo000rsquo000

years

human intrusion

Changes acting on these elements

Predictability of changesinto the future



Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion



No confidence in long-term reliability of human society(geology more stable than human society)


Passive barriers with multiple safety functionsSwitzerland Importance of very low permeability host rock

System with multiple safety barriers- Waste matrix (UO2MOX glass)- Canister- Bentonite backfill- Opalinus Clay + other claystones

Situated in stable environment- At great depth- Stable geological environment- No resource conflicts

Provides Safety Functions- Long-lived system (stability)- Isolation from human environment- Confinement and decay within

barrier system- Attenuation of releases to

environment (low doses)


Geological investigations from the surface hellip

2D-Seismics (Laumlgern) Borehole (Benken)


hellip and from the underground (Underground Rock Laboratory Mont Terri)

Opalinus Clay

Mont Terri Project


Dose calculations (example project Opalinus clay)Deterministic amp probabilistic analyses

SF

HLW

ILW


Times amp doses in perspective (example Switzerland)

1) for a well designed repository (well chosen site adequate design)

Some of the porewaterconstituents originating from the time of depo-

sition are still there today


Different possibilities to achieve a safe system

Waste form Canister Backfill Host rock Geological

situation

Confinement 1) - 2) - 3)

Retention amp slow release bullbullbull - 4) - 5)

Isolation amp stability

1) Containment of UO2-pellets in hulls (USA)2) Containment in canister of special material (Sweden Finland USA)3) Containment in host rock (salt Germany)4) Retention due to geochemical processes (several)5) Retention in impermeable host rock (clay host rock Belgium France Switzerland)

Differences of Importance of individual Barrier Elements to achieve sufficient performance of the different Safety Functions




situation







Repository in Salt (Gorleben Salt Dome Germany)


Repository in Salt (eg Germany)

Key importance of the saltas barrier (no water flow under normal conditions)

Container amp waste matrixfor post-closure safety of low priority

Backfill with salt provides suitable interface between waste package and host rock


Repository in Granite (Sweden amp Finland)Long-term isolation due to copper canister

Cladding tube

Spent nuclear fuel

Bentonite clay

500 m

Fuel pellet ofuranium dioxide

Copper canister with cast iron insert

Crystallinebedrock

Surface portion of deep repository

Underground portion of deep repository


Copper canister (eg SKB POSIVA)


Yucca Mountain (USA) climate and geology hellipThe dryness of the dessert is not sufficient


Yucca Mountain hellip and engineered barriersTherefore complex system of engineered barriers complement unsaturated host rock (tuff)


Status of different programmes (examples)

HLW repository LILW repository(deep disposal)


From how to where

Site selection


Decision - making different groups and their interaction

PolicyPolitics

IndustryImplementer

Public

Regulation(Supervision Expertise)

Formal interaction and involvement of (perception by) the public


Site selection process in Switzerland Key features The Federal Government (Federal Office of Energy) is taking a

leading role in the site selection process in Switzerland The Sectoral Plan (concept rules) was developed following a broad

participatory process (concept issued in April 2008 by Government) Stakeholder participation and their respective roles are clearly

defined in the Sectoral plan (concept) Site selection follows a stepwise process

- Stage 1 Siting regions proposed by Nagra based on safety and technical feasibility criteria review amp compilation of spatial planning information

- Stage 2 lsquoregional participationrsquo (incl socio-economic aspects) location of surface facilities considering local aspects amp concerns based on broad evaluation proposal of ge 2 sites for HLW and LILW by Nagra

- Stage 3 Field investigations and selection of 1 site for HLW and LLLW by Nagra preparation of general site license applications

Afterwards general license procedure (authority review government decision ratification by parliament facultative national referendum)


Process amp responsibilities Criteria (safety environmental

impact socio-economic issues)

Sectoral Plan Deep Geological Repositories


Sources of geological information hellip Outcrops surface (rock faces valleys hellip) Tunnels Boreholes Seismics 2 URLs


Sectoral plan

Developing proposals for siting regions (Stage 1)

1 Waste allocation to the two repositories (LILW HLW)

2 Definition of the barrier concept and safety concept development of requirements on geology and repository layout

3 Identification of suitable large-scale geologic-tectonic units (stability tectonic overprint geometry)

4 Within these regions identification of potentially suitable host rocks (barrier performance construction feasibility)

5 Identification of suitable configurations of the host rocks regions (sufficient extent suitable depth amp little disturbed)

6 Further factors assessment of land use planning (hellip )


Stepwise narrowing-in (HLW)Stability amp large-scale geometry Suitable geotectonic units

Barrier performance amp construction feasibility Suitable host rocksamp their occurrence

Host rocks of sufficient extent appropriate depth and little disturbed (local tectonics) Siting regions


Proposed siting regions (LILW- amp HLW-repository)


Current status of site selection process (Switzerland)

Announcement of proposals (6 November 2008) received broad media coverage ndash in general positive

Since 15 November Information (amp discussion) in the proposed regions amp Germany about 15 eventsGenerally in friendly environment site selection process accepted but nobody is enthusiastic to be a potential region

Review amp review meetings have started Decision on siting regions

in about 2frac12 years


National amp regional campaigns to raise awareness


Summary amp conclusions Waste management involves a spectrum of activities

treatmentcharacterisation interim storage final disposal Broad agreement for long-lived waste disposal in deep geological

repositories is the accepted end-point Disposal of LILW is an established technology many repositories

are in operation since many years The scientific basis and the technology is also available to

implement HLW repositories (a range of different designs are considered depending upon the geology available)

Implementation of HLW repositories has started in a few countries Progress with implementation is slower than originally expected the

societal process of decision-making requires in most countries much time

The End

Thank you


Nuclear Power in Switzerland5 Nuclear Power Plants (3220 MWe)KKL Leibstadt (1984) 1165 MWeKKB-I Beznau (1969) 365 MWeKKB-II Beznau (1971) 365 MWeKKG Goesgen (1979) 970 MWeKKM Muehleberg (1971) 355 MWe

0 100 200 300 km



Hydro (Rivers)

Hydro (Reservoirs)

Convential thermal

Nuclear

Consumption








Source IAEA PRIS






many countries

















































river

Handling gallery


xhau

st

Air inle

t

Watertable level






















(amp SFL)












Ramp


Shaft

Canister



Disposal tunnelILW









Host rock



Geosphere








Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion





Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion
















Opalinus Clay

Mont Terri Project



SF

HLW

ILW









situation









situation















Cladding tube

Spent nuclear fuel

Bentonite clay

500 m



Crystallinebedrock













From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you



Hydro (Rivers)

Hydro (Reservoirs)

Convential thermal

Nuclear

Consumption








Source IAEA PRIS






many countries

















































river

Handling gallery


xhau

st

Air inle

t

Watertable level






















(amp SFL)












Ramp


Shaft

Canister



Disposal tunnelILW









Host rock



Geosphere








Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion





Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion
















Opalinus Clay

Mont Terri Project



SF

HLW

ILW









situation









situation















Cladding tube

Spent nuclear fuel

Bentonite clay

500 m



Crystallinebedrock













From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you






Source IAEA PRIS






many countries

















































river

Handling gallery


xhau

st

Air inle

t

Watertable level






















(amp SFL)












Ramp


Shaft

Canister



Disposal tunnelILW









Host rock



Geosphere








Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion





Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion
















Opalinus Clay

Mont Terri Project



SF

HLW

ILW









situation









situation















Cladding tube

Spent nuclear fuel

Bentonite clay

500 m



Crystallinebedrock













From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you






many countries

















































river

Handling gallery


xhau

st

Air inle

t

Watertable level






















(amp SFL)












Ramp


Shaft

Canister



Disposal tunnelILW









Host rock



Geosphere








Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion





Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion
















Opalinus Clay

Mont Terri Project



SF

HLW

ILW









situation









situation















Cladding tube

Spent nuclear fuel

Bentonite clay

500 m



Crystallinebedrock













From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you
















































river

Handling gallery


xhau

st

Air inle

t

Watertable level






















(amp SFL)












Ramp


Shaft

Canister



Disposal tunnelILW









Host rock



Geosphere








Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion





Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion
















Opalinus Clay

Mont Terri Project



SF

HLW

ILW









situation









situation















Cladding tube

Spent nuclear fuel

Bentonite clay

500 m



Crystallinebedrock













From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you





















(amp SFL)












Ramp


Shaft

Canister



Disposal tunnelILW









Host rock



Geosphere








Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion





Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion
















Opalinus Clay

Mont Terri Project



SF

HLW

ILW









situation









situation















Cladding tube

Spent nuclear fuel

Bentonite clay

500 m



Crystallinebedrock













From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you











Ramp


Shaft

Canister



Disposal tunnelILW









Host rock



Geosphere








Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion





Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion
















Opalinus Clay

Mont Terri Project



SF

HLW

ILW









situation









situation















Cladding tube

Spent nuclear fuel

Bentonite clay

500 m



Crystallinebedrock













From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you









Host rock



Geosphere








Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion





Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion
















Opalinus Clay

Mont Terri Project



SF

HLW

ILW









situation









situation















Cladding tube

Spent nuclear fuel

Bentonite clay

500 m



Crystallinebedrock













From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you








Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion





Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion
















Opalinus Clay

Mont Terri Project



SF

HLW

ILW









situation









situation















Cladding tube

Spent nuclear fuel

Bentonite clay

500 m



Crystallinebedrock













From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you



Ecological change



100

10rsquo000

1rsquo000rsquo000

years

human intrusion
















Opalinus Clay

Mont Terri Project



SF

HLW

ILW









situation









situation















Cladding tube

Spent nuclear fuel

Bentonite clay

500 m



Crystallinebedrock













From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you













Opalinus Clay

Mont Terri Project



SF

HLW

ILW









situation









situation















Cladding tube

Spent nuclear fuel

Bentonite clay

500 m



Crystallinebedrock













From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you



SF

HLW

ILW









situation









situation















Cladding tube

Spent nuclear fuel

Bentonite clay

500 m



Crystallinebedrock













From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you









situation









situation















Cladding tube

Spent nuclear fuel

Bentonite clay

500 m



Crystallinebedrock













From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you




situation















Cladding tube

Spent nuclear fuel

Bentonite clay

500 m



Crystallinebedrock













From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you










Cladding tube

Spent nuclear fuel

Bentonite clay

500 m



Crystallinebedrock













From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you











From how to where

Site selection



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you



PolicyPolitics

IndustryImplementer

Public



















Sectoral plan






























The End

Thank you

















Sectoral plan






























The End

Thank you























The End

Thank you

management of radioactive wastes - upcoming events » …€¦ · a hard rock : limestone, granite...

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