Week 3: Electronic Marketplaces MIS 3580: Internet-Enabled Supply Chains Prof. Sunil Wattal.
Ozarde - International Atomic Energy Agency | Atoms for ... RADIOACTIVE WASTE MANAGEMENT PROGRAMME...
Transcript of Ozarde - International Atomic Energy Agency | Atoms for ... RADIOACTIVE WASTE MANAGEMENT PROGRAMME...
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INDIAN RADIOACTIVE WASTE
MANAGEMENT PROGRAMME
ACKNOWLEDGEMENT
1. N.K. BANSAL
2. KANWAR RAJ
3. P.K. WATTAL
4. P.K. NARAYAN
P.D. OZARDE
Superintendent, WMF Trombay
Nuclear Recycle Group
Bhabha Atomic Research Centre
Trombay, Mumbai
Golden Jubilee Year of Indian Nuclear Energy Programme
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PROJECTED GROWTH OF NUCLEAR ENERGY IN INDIA
20,3352018-2022
16,3352013-2017
9,3352008-2012
3,9402006-2007
2,720Current (2002-2003)
INSTALLED CAPICITY MWeYEAR
CONTRIBUTION OF
2500FBR
235INNOVATIVE REACTOR (AHWR)
8000LWR
9,600PHWR
THE PROJECTED GROWTH OF NUCLEAR ENERGY COUPLED WITH CURRENT
RECYCLE POLICY SIGNIFY AND ORDER OF MAGNITUDE INCREASE INWASTE
ARRISING RIGHT THROUGH FRONT END TO BACK END OF THE FUEL CYCLE
CALL FORNEW STRATAGY, MANAGEMENT APPROCH ANDIMPROVED
TECHNOLOGY.
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National Policy for
Radioactive Waste Management
• Discharges to environment
– As Low As Reasonably Achievable (ALARA)
• Low and Intermediate Level Waste
– Near Surface Disposal Facility (NSDF)
• High Level and Alpha Waste
– Immobilization (WIPs)
– Interim Storage (SSSF)
– Deep Geological Repository (Planned)
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4. Spent Radiation Sources
- Return to original supplier or
- Reuse/recycle or
- Condition and dispose
- On no cost basis
5. Collocation of NSDF and nuclear installation
- Avoiding long distance transportation
6. Collocation of reprocessing and Vitrification plants
7. Period of control of NSDF
- Active control (100 years)
- Passive control (200 years)
National Policy for
Radioactive Waste Management
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MANAGEMENT OF RADIOACTIVE WASTE
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MANAGEMENT OF RADIOACTIVE WASTE
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PHWR (4 X 220 MWe), Isotope facility
PHWR (2 X 220 MWe)
PHWR (2 X 220 MWe)
PHWR (2 X 220 MWe)
1972
1989
1993
2000
Rajasthan
Narora
Kakrapar
Kaiga
INLAND
PHWR (2 X 170 MWe)
Fuel Reprocessing Plant, Research Laboratories
Research Reactors (FBTR)
WIP under construction
1984KalpakkamCOASTAL
BWR (2 x 160 New)
Fuel Reprocessing Plant, Fuel Fabrication Plant
WIP
1969TarapurCOASTAL
Research Reactors, Fuel Fabrication
Fuel Reprocessing, Research Laboratories
Isotope Production, WIP
1956TrombayCOASTAL
Nuclear facilityYear ofcommissioning
Site
WASTE MANAGEMENT FACILITIES IN INDIA
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Radioactive Waste Management Facilities in India
EEDisused Radiation Sources:
Conditioning & Disposal
PPEPPEEIncineration
PPPPPPECompaction
CEOrganic Waste Treatment
CEAir Cooled vault for interim
storage of vitrified HLW
PCActinide Separation Plant
CEEVitrification of HLW
PEPECECPolymerisation of spent Ion
Ex. Resin
CE(1)E
(2)C
Ion Ex. Treatment for ILW
EEEEEEECementation of Chemical
sludges, etc.
SteamSolarSteamEvaporation
EEMembrane Separation
EEEEEEEChemical Treatment of LLW
KaigaKakraparKalpakkamNaroraRajasthanTarapurTrombay
E - ExistingC - Under constructionP - Planned
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Imm
obili
sation
Interim
Sto
rage
Deep Disposal
HLW
3-STAGE INDIAN PROGRAMME FOR MANAGEMENT OF HIGH LEVEL WASTE
Canister
Welding
Glass Pouring
Shielded
Transport
Cask
Air cooled Storage
Deep Geological
RepositoryHLW From Reprocessing
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Vitrification
1st Generation Plants : Metallic Melters
Tarapur, Trombay
2nd Generation Plants : Ceramic Melters
Tarapur, Kalpakkam, Trombay
3rd Generation Plants : Ceramic Melters & Cold Crucibles
Tarapur, Kalpakkam
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Four Important Developments of 2004
1. Recycle
2. Legacy Waste
3. Underground Research Laboratory (URL)
4. Knowledge Management Group
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Recycle
Conditioning & Disposal last resort
Emphasis on Recover & Reuse to the extent possible
1.1 Fission products :
137Cs : Phase I - From ILW (Industrial Scale)
Phase II - From HLW (Pilot Plant Scale)
90Sr (Laboratory Scale)
1.2 Major Actinides : U, Pu (Industrial Scale) Resource Constraint
Minor Actinides : Plant under installation
1.3 Zircalloy Hulls
Phase I – Compaction
Phase II – Decontamination and Remelting for reuse
1.4 Solvent for Reprocessing
1.5 Acid from HLW
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Management of Legacy Waste
Phase I : Old ILW
Phase II : Old HLW
Salient Features of Phase II Old HLW
Characteristics :• High salt load
• Adverse Inactive / Active salt ratio
• Problematic constituents
Vitrification experience at Trombay• Lead Borosilicate Glass
• Barium Borosilicate Glass
New Treatment Scheme
Pilot Plant Experience
Legacy Waste
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Underground Research Laboratory (2003-2012)
Depth : 200m to 500m
Location : Southern India
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Objectives of an Underground Research Laboratory
1. To develop the excavation technology &
methodology for optimization of
construction induced damage in
monolithic rock mass.
• Refinement of existing non-destructive
methods of rock mass assessment
• Development of instrumentation and
methodology for in-situ stress determination
• Optimization of disposal tunnel and pit shape,
geometry, extent etc.
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Objectives of an Underground Research Laboratory
2. Test, evaluate and model the behavior of the
various components of Engineered Barrier
System (EBS) under heat and moisture and their
coupling with geological barrier.
• Simulated overpack test (waste form is simulated by a
heater) to understand behavior of buffer, backfill and
rocks under thermal loading
• Tunnel scale test to evaluate supports and seals at
elevated temperature.
• Microbiological degradation of barriers
• Gas migration test through EBS and fractures
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Objectives of an Underground Research Laboratory
3. Development of suitable seal, grouts, lining
and support and test their behavior under
repository conditions.
• Methodology development for fracture sealing
• Methodology, technology and instrumentation
for disposal tunnel sealing
4. Development of technology and
instrumentation for waste transfer,
emplacement and remote handling systems
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Objectives of an Underground Research Laboratory
5. To validate models for safety assessment
• Hydrogeological models for estimation of thewater ingress
• Solute transport and radionuclides migrationthrough EBS and fractures
• Performance assessment and Service lifeprediction for various components of EBSunder repository conditions
6. To demonstrate feasibility and safety ofgeological disposal including publicacceptance and regulatory aspects
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Knowledge Management Group
1. To create sustainable pool of technocrats in all fields of nuclear energy programme
2. To upgrade necessary infrastructure in conventional industries to meet future challenges from nuclear industry
3. To transfer state of art technologies developed in house for betterment of conventional industries
4. To accelerate public awareness programme
• Universities and Academic Institutions
• Journalists & Media Representatives
• General Public - Rural / Urban
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Thank
You