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Securing India’s energy future

                             Anil Kakodkar



           IIM, Bangalore,
           January 4, 2012
Securing energy for India’s future is a major challenge

                    World   OECD      Non-OECD            India    India
                                     (developing world)           of our dream
Population
(billion)           6.7     1.18        5.52              1.2       1.6
                                                                   (stabilised)
Annual
av. per capita    ~2800     ~9000      ~1500              ~675       5000
Electricity (kWh)

Annual
Electricity
Generation          18.8     10.6         8.2             0.811      8.0
(trillion kWh)

Carbon-di-oxide
Emission            30       13          17                1.7        ?
(billion tons/yr)



India alone would need around 40% of present
global electricity generation to be added to reach
average 5000 kWh per capita electricity generation
Number of years a domestic non-renewable energy source (as known today) can last
         at 5000 kWh/capita electricity consumption in India (8 trillion units)

     Coal        Hydro-carbon         Uranium               Uranium              Thorium
                                    once-through            recycle



    11.5                 ----           0.36                  18.5               >170


   Non-                             Electricity generation potential from renewable sources
                  Renewable                   in India ( as fraction of 8 trillion units)
renewable

  WHILE WE MUST MAKE                    Hydro       Other renewables                  solar
                                                         (wind+biomass)
    FULL USE OF ALL
   AVAILABLE ENERGY
    RESOURCES ONLY
                                        0.075               0.0225                    1.0*
  THORIUM AND SOLAR                 *Would need ~45,000 sq.km which corresponds to a
 ENERGY IS SUSTAINABLE              fourth of barren and uncultivable land in India
    IN THE LONG RUN
(FUSION ENERGY NOT CONSIDERED FOR
          THE PRESENT)
We do not know how
                                      close we are to the
                                         tipping point.
                                     However we need to
                                      act now to secure
                                        survival of our
                                     future generations.

                                      Incidentally both
 Global average temperature over
.
last one and a half century            nuclear and solar
showing a more or less steady         cause least carbon-
increase over the last fifty years
or so. The fluctuations and their      di-oxide emission
cycles can be correlated with
various events like solar cycles
Stage 1:
                                   Since Thorium does
                                   not have a naturally
                                   occurring      fissile
                                   content, one has to
                                   begin nuclear energy
                                   program          with
                                   Uranium.

                                   Stage 2:
                                   For   faster  growth,
                                   plutonium breeding in
                                   fast    reactors   is
                                   necessary


Stage 3:
After generation capacity is
sufficiently enlarged through
fast reactors,     Thorium can
sustain    the       generation
capacity with a wide range of
choices, lower minor actinide
burden        and        greater
proliferation resistance
Three Stage Indian Nuclear Power Programme
                                                                                               Globally Advanced                       Globally Unique
         100
          95                                            91    90
                                                  90                 89

                                                                                               Technology
               90                     84    86                            85
                                84                                              83
                                                                                     82
Availability




               85          79
               80     75

                           World class
               75
               70
               65
               60          performance
               55
               50
                    1997- 1998- 1999- 2000- 2001- 2002- 2003- 2004- 2005- 2006- 2007- 2008-
                     98    99    00    01    02    03    04    05    06    07    08    09




  Stage – I                                                                                   Stage - II                               Stage - III
  PHWRs                                                                                        Fast Breeder Reactors                   Thorium Based Reactors
  • 18 – Operating (4460 MWe)                                                                 • 40 MWth FBTR - Operating since
  • 4– 700 MWe units under                                                                      1985                                   • 30 kWth KAMINI- Operating
  construction (2800 Mwe)                                                                     • Technology Objectives realised
  •Several 700 MWe units                                                                      • 500 MWe PFBR-                          • 300 MWe AHWR-
  planned
                                                                                                Under Construction                      ready for deployment
  LWRs                                                                                        • Pre-project activities for two
  • 2 --BWRs Operating (320                                                                     more FBRs approved         • Availability of ADS can enable
  MWe)                                                                                        • TOTAL POWER POTENTIAL 530  early introduction of Thorium on a
  • 2 -- VVERs under                                                                                                       large scale
                                                                                                GWe (including 300 GWe with Thorium)
       construction (2000 Mwe)                                                                No additional mined uranium ENERGY POTENTIAL IS
  • Several LWR Units planned                                                                  is needed for this scale up   VERY LARGE
Strategy for long-term energy security

                                                                    The deficit is practically
                               1400
                                                                      wiped out in 2050
                               1300    LWR import: 40 GWe
                               1200     Period: 2012-2020
                               1100
                                                                                         FBR using spent
                               1000                                                      fuel from LWR
    Installed capacity (GWe)




                               900
                                                                                         LWR (Imported)
                               800
                                                                                         Nuclear (Domestic
                               700                                                       3-stage
                                      Projected                                          programme)
                               600
                                      requirement*
                               500                                                        Hydrocarbon
                               400
                                                                                          Coal domestic
                               300
                               200
                                                                                          Non-conventional
                               100
                                 0                                                        Hydroelectric
                                      2010      2020     2030     2040            2050
                                                                *Ref: “A Strategy for Growth of Electrical Energy in
                                                       Year
*   - Assuming 4200 kcal/kg                                     India”, document 10, August 2004, DAE
Energy Source Death Rate (deaths per TWh)

Coal world average            161 (26% of world energy, 50% of electricity)
Coal China                    278
Coal USA                        15
Oil                             36 (36% of world energy)
Natural Gas                       4 (21% of world energy)
Biofuel/Biomass                  12
Peat                             12
Solar (rooftop)                   0.44 (less than 0.1% of world energy)
Wind                              0.15 (less than 1% of world energy)
Hydro                             0.10 (Europe death rate, 2.2% of world energy)
Hydro - world including Banqiao) 1.4 (about 2500 TWh/yr and 171,000 Banqiao dead)
Nuclear                           0.04 (5.9% of world energy)

http://nextbigfuture.com/2011/03/deaths-per-twh-by-energy-source.html

              Risks with nuclear energy are the least
Projected health consequences from low
   doses to large sections of population are
                 questionable
IN CASE OF CHERNOBYL

ESTIMATED CONSEQUENCES
AN ESTIMATE IN 2006—93,000 WILL DIE DUE TO CANCER UP TO THE
YEAR2056
ANOTHER ESTIMATE IN 2009---985,000 DIED TILL 2004
                                                Driven by
ACTUAL CONSEQUENCE                         conservative linear
TOTAL DEATHS;                                 no threshold
62 (47 PLANT, 15 DUE TO THYROID CANCER )   principle (which is
ACUTE RADIATION SYNDROME;                   not substantiated
134 (OUT OF WHICH 28 HAVE DIED)              surveys in high
INCREASED CANCER INCIDENCE;                 natural radiation
AMONG RECOVERY WORKERS                     background areas)
THYROID CANCER; (CURABLE, WAS AVOIDABLE)    we tend to create
6000 ( 15 HAVE DIED)                        avoidable trauma
                                             in public mind
 There is already a large used uranium fuel inventory (~270,000
  tons as per WNA estimate)

 While the spent fuel would be a sufficiently large energy
  resource if recycled, its permanent disposal is in my view an
  unacceptable security and safety risk (plutonium mine?)

 We need to adopt ways to liquidate the spent fuel inventory
  through recycle

 France today recycles entire spent fuel arising. Recycle is a
  credible option.
 Development of Partitioning and Transmutation technologies can
  in principle effectively address long term waste management
  challenge.


         Waste management challenge can be
           effectively met through recycle
The Indian Advanced Heavy Water Reactor (AHWR),
a quick, safe, secure and proliferation resistant solution for the
                      energy hungry world
AHWR is a 300 MWe vertical pressure tube type, boiling light water cooled and heavy water
moderated reactor (An innovative configuration that can provide low risk nuclear energy using
available technologies)

                                Major design objectives

                                  Significant fraction of Energy from
                                   Thorium                                   Top Tie Plate

                                                                                  Displacer
                                                                          Water   Rod
                                  Several passive features               Tube
                                       3 days grace period                Fuel
                                                                           Pin
                                       No radiological impact
  AHWR can be
  configured to accept a          Passive shutdown system to address
  range of fuel types              insider threat scenarios.
  including LEU, U-Pu ,
  Th-Pu , LEU-Th and              Design life of 100 years.
  233U-Th in full core                                                     Bottom Tie Plate
                                  Easily replaceable coolant channels.
                                                                           AHWR Fuel assembly
AHWR 300-LEU is a simple 300 MWe system fuelled
with LEU-Thorium fuel, has advanced passive safety
     features, high degree of operator forgiving
characteristics, no adverse impact in public domain,
 high proliferation resistance and inherent security
                       strength.
                                                                          600
                                   Peak clad




                                                   Clad temperature (K)
                                                                                          10 sec delay
                             temperature hardly                           590
                                                                                          5 sec delay
                               rises even in the                          580             2 sec delay
                              extreme condition
                             of complete station                          570
                                 blackout and
                                                                          560
                              failure of primary
                                and secondary                             550
                                   systems.
                                                                                0   200 400 600 800 1000
  Reactor Block Components                                                             Time (s)

AHWR300-LEU provides a robust design against
external as well as internal threats, including insider
malevolent acts. This feature contributes to strong
security of the reactor through implementation of
technological solutions.
PSA calculations for AHWR indicate practically zero
  probability of a serious impact in public domain
Plant familiarization &                                      Level-3 : Atmospheric Dispersion With                                          SWS: Service
identification of design                                             Consequence Analysis                                                   Water System
                                                                                                                                            APWS: Active
aspects important to                                                                                                                        Process Water
severe accident                                                                                                                             System

                                                                      Release from Containment                                              ECCS HDRBRK:
                                                                                                                                            ECCS Header
                                                                                                                                            Break
PSA level-1 : Identification                                                                                                                LLOCA: Large
of significant events with                                                                                                                  Break LOCA

large contribution to CDF                                    Level-2 : Source Term (within                                          SLOCA
                                                                                                                                            MSLBOB: Main
                                                                                                                                            Steam Line
                                                             Containment) Evaluation through            SWS                         15%     Break Outside
                                                                                                        63%
                                                             Analysis                                                                       Containment
                                                                                                                   Contribution to CDF
                                            Level-1, 2 & 3 PSA activity block diagram



                             10-10
                              10
                                -10
   Frequency of Exceedence




                             10-11
                              10
                                -11




                                 -12
                             10-12
                              10


                             10-13
                              10
                                -13




                             10-14
                              10
                                -14




                                   110
                                     mSv        0.1 Sv        1.0 Sv        10 Sv
                                       -3           -2           -1           0
                                                   10          10            10
                                            Thyroid Dose (Sv) at 0.5 Km                          Iso-Dose for thyroid -200% RIH + wired shutdown
   Variation of dose with frequency exceedence                                               system unavailable (Wind condition in January on western
                                                                                                                                                      14
 (Acceptable thyroid dose for a child is 500 mSv)                                                                    Indian side)
STRONGER PROLIFERATION
Amount of Plutonium in spent fuel per unit energy

                                                    30


                                                    25
                                                                       Total
                                                                       Fissile
                                                                                         RESISTANCE WITH AHWR 300-LEU
                                                    20
                  (kg/TWhe)




                                                    15                                Much lower Plutonium production.
                                                    10

                                                                                      Plutonium in spent fuel contains lower
                                                                                      fissile fraction, much higher 238Pu content
                                                     5


                                                     0
                                                          Modern
                                                         MODERN       AHWR300-
                                                                     AHWR300-LEU      which causes heat generation & Uranium in
                                                            LWR
                                                           LWR
                                                                            LEU       spent fuel contains significant 232U content
                                                                                      which leads to hard gamma emitters.
    238Pu                                                3.50    %   9.54         %
    239Pu                                                51.87   %   41.65        %
    240Pu                                                23.81   %   21.14        %   The composition of the fresh as well as the
    241Pu                                                12.91   %   13.96        %   spent fuel of AHWR300-LEU makes the fuel
                                                                                      cycle inherently proliferation resistant.
    242Pu                                                7.91    %   13.70        %
    232U                                                 0.00    %   0.02         %
                                                                                      Uranium in spent fuel contains about 8%
    233U                                                 0.00    %   6.51         %   fissile isotopes, and hence is suitable for
    234U                                                 0.00    %   1.24         %   further energy production through reuse in
    235U                                                 0.82    %   1.62         %   other reactors. Further, it is also possible to
    236U                                                 0.59    %
                                                                                      reuse the Plutonium from spent fuel in fast
                                                                     3.27         %
    238U                                                 98.59   %   87.35        %
                                                                                      reactors.
Present deployment                                           MOX                  Thorium
 Of nuclear power

                                                         Reprocess
                                    Thermal              Spent Fuel     Fast
            Enrichment              reactors                           Reactor
 Uranium                   LEU
               Plant

                                    For growth in
                                       nuclear
             LEU Thorium                                                Recycle
 Thorium                             generation
                 fuel
                                   beyond thermal
                                  reactor potential                                  233U

                                                                                   Thorium
   LEU-
                                  Nuclear power with
 Thorium                         greater proliferation
                                       resistance

             Safe &                                                   Thorium
             Secure
            Reactors                                                  Reactors
           For ex. AHWR                   Recycle                     For ex. Acc.
                                                                      Driven MSR
                                                            Thorium
CHALLENGES IN SOLAR TECHNOLOGY
Drive capital costs down

Low cost energy storage systems

Solar biomass hybrids

Solar thermal photovoltaic hybrids

Large solar thermal systems not dependent on
availability of water

Technology initiatives
     1.Higher efficiency / non-toxic PV materials
     2.High temperature photovoltaics
     3.Self cleaning abrasion resistant surfaces
     4.Recycle of Carbon-di-oxide to fluid hydrocarbon substitutes
     5. ---------------
Sustainable development of energy sector
                      Transition to Fossil Carbon Free Energy Cycle
                                        Carbon/              ENERGY
GREATER                  Fossil         Hydrocarbons
                                                              CARRIERS
SHARE FOR                Energy                Electricity   (In storage or       WASTE
NUCLEAR IN               Resources                              transportation)
ELECTRICITY                                                                       • CO2
                                               Electricity
SUPPLY                                                       • Electricity
                                                                                  • H2O
                                                             • Fluid fuels
REPLACE                                                                           • Other
FOSSIL                    Hydrogen                           (hydro-carbons/       oxides and
HYDRO-                                                                             products
                                           Sun                 hydrogen)
CARBON IN A
PROGRESSIVE
MANNER                                             CH4              Fluid
                     Nuclear                                        Hydro
                                                                    carbons
RECYCLE              Energy                                                       CO2
                                                                 chemical
CARBON-              Resources           Biomass                  reactor
DIOXIDE                                                  CO2
                                                                                           Other
DERIVE MOST                                                                               recycle
OF PRIMARY                  Nuclear Recycle
                                                                                          modes
ENERGY         Sustainable Waste Management Strategies
THROUGH
SOLAR &     Urgent need to reduce use of fossil carbon in a progressive manner
NUCLEAR
Thank
 you
Reduced Plutonium generation                                              High 238Pu fraction and low fissile content
Amount of Plutonium in spent fuel per unit energy

                                                    30                                                     of Plutonium
                                                                    Total                                                                                                                      238Pu
                                                                    Fissile                                                                                                                    239Pu
                                                    25
                                                                                                                                                                                                240Pu

                                                                                                                                                                                                241Pu
                                                    20                                                                                                                                          242Pu
                  (kg/TWhe)




                                                    15                                                 MODERN                                          AHWR300-LEU
                                                                                                        LWR
                                                                                         238Pu               3.50               %                238Pu                9.54               %
                                                    10                                   239Pu               51.87              %                239Pu                41.65              %
                                                                                         240Pu               23.81              %                240Pu                21.14              %
                                                     5                                   241Pu               12.91              %                241Pu                13.96              %
                                                                                         242Pu               7.91               %                242Pu                13.70              %
                                                     0
                                                         MODERN   AHWR300-LEU   The French N4 PWR is considered as representative of a modern LWR.. The reactor has been referred from “Accelerator-driven
                                                          LWR                   Systems (ADS) and Fast Reactor (FR) in Advanced Nuclear Fuel Cycles”, OECD (2002)




                                                    STRONGER PROLIFERATION RESISTANCE
                                                           WITH AHWR 300-LEU
                                                             MUCH LOWER PLUTONIUM PRODUCTION
                                                            Much Higher 238Pu & Lower Fissile Plutonium
Presence of 232U in uranium from spent fuel           The

                                                         232U   composition
                                                         233U

                                                         234U
                                                                of the fresh
                                                         235U

                                                         236U
                                                                as well as the
                                                         238U



                                       AHWR300-LEU
                                                                spent fuel of
          MODERN
           LWR
                                                                AHWR300-LEU
   232U                         232U       0.02      %
              0.00    %
                                233U       6.51      %
   233U       0.00    %                                         makes the
   234U                         234U       1.24      %
              0.00    %
   235U       0.82    %         235U       1.62      %          fuel cycle
   236U                         236U       3.27      %
              0.59    %
   238U       98.59   %         238U       87.35     %          inherently

Uranium in the spent fuel contains about 8% fissile             proliferation
isotopes, and hence is suitable to be reused in other
reactors. Further, it is also possible to reuse the             resistant.
Plutonium from spent fuel in fast reactors.

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Securing india’s energy future

  • 1. Securing India’s energy future Anil Kakodkar IIM, Bangalore, January 4, 2012
  • 2.
  • 3. Securing energy for India’s future is a major challenge World OECD Non-OECD India India (developing world) of our dream Population (billion) 6.7 1.18 5.52 1.2 1.6 (stabilised) Annual av. per capita ~2800 ~9000 ~1500 ~675 5000 Electricity (kWh) Annual Electricity Generation 18.8 10.6 8.2 0.811 8.0 (trillion kWh) Carbon-di-oxide Emission 30 13 17 1.7 ? (billion tons/yr) India alone would need around 40% of present global electricity generation to be added to reach average 5000 kWh per capita electricity generation
  • 4. Number of years a domestic non-renewable energy source (as known today) can last at 5000 kWh/capita electricity consumption in India (8 trillion units) Coal Hydro-carbon Uranium Uranium Thorium once-through recycle 11.5 ---- 0.36 18.5 >170 Non- Electricity generation potential from renewable sources Renewable in India ( as fraction of 8 trillion units) renewable WHILE WE MUST MAKE Hydro Other renewables solar (wind+biomass) FULL USE OF ALL AVAILABLE ENERGY RESOURCES ONLY 0.075 0.0225 1.0* THORIUM AND SOLAR *Would need ~45,000 sq.km which corresponds to a ENERGY IS SUSTAINABLE fourth of barren and uncultivable land in India IN THE LONG RUN (FUSION ENERGY NOT CONSIDERED FOR THE PRESENT)
  • 5. We do not know how close we are to the tipping point. However we need to act now to secure survival of our future generations. Incidentally both Global average temperature over . last one and a half century nuclear and solar showing a more or less steady cause least carbon- increase over the last fifty years or so. The fluctuations and their di-oxide emission cycles can be correlated with various events like solar cycles
  • 6. Stage 1: Since Thorium does not have a naturally occurring fissile content, one has to begin nuclear energy program with Uranium. Stage 2: For faster growth, plutonium breeding in fast reactors is necessary Stage 3: After generation capacity is sufficiently enlarged through fast reactors, Thorium can sustain the generation capacity with a wide range of choices, lower minor actinide burden and greater proliferation resistance
  • 7. Three Stage Indian Nuclear Power Programme Globally Advanced Globally Unique 100 95 91 90 90 89 Technology 90 84 86 85 84 83 82 Availability 85 79 80 75 World class 75 70 65 60 performance 55 50 1997- 1998- 1999- 2000- 2001- 2002- 2003- 2004- 2005- 2006- 2007- 2008- 98 99 00 01 02 03 04 05 06 07 08 09 Stage – I Stage - II Stage - III PHWRs Fast Breeder Reactors Thorium Based Reactors • 18 – Operating (4460 MWe) • 40 MWth FBTR - Operating since • 4– 700 MWe units under 1985 • 30 kWth KAMINI- Operating construction (2800 Mwe) • Technology Objectives realised •Several 700 MWe units • 500 MWe PFBR- • 300 MWe AHWR- planned Under Construction ready for deployment LWRs • Pre-project activities for two • 2 --BWRs Operating (320 more FBRs approved • Availability of ADS can enable MWe) • TOTAL POWER POTENTIAL 530 early introduction of Thorium on a • 2 -- VVERs under large scale GWe (including 300 GWe with Thorium) construction (2000 Mwe) No additional mined uranium ENERGY POTENTIAL IS • Several LWR Units planned is needed for this scale up VERY LARGE
  • 8. Strategy for long-term energy security The deficit is practically 1400 wiped out in 2050 1300 LWR import: 40 GWe 1200 Period: 2012-2020 1100 FBR using spent 1000 fuel from LWR Installed capacity (GWe) 900 LWR (Imported) 800 Nuclear (Domestic 700 3-stage Projected programme) 600 requirement* 500 Hydrocarbon 400 Coal domestic 300 200 Non-conventional 100 0 Hydroelectric 2010 2020 2030 2040 2050 *Ref: “A Strategy for Growth of Electrical Energy in Year * - Assuming 4200 kcal/kg India”, document 10, August 2004, DAE
  • 9. Energy Source Death Rate (deaths per TWh) Coal world average 161 (26% of world energy, 50% of electricity) Coal China 278 Coal USA 15 Oil 36 (36% of world energy) Natural Gas 4 (21% of world energy) Biofuel/Biomass 12 Peat 12 Solar (rooftop) 0.44 (less than 0.1% of world energy) Wind 0.15 (less than 1% of world energy) Hydro 0.10 (Europe death rate, 2.2% of world energy) Hydro - world including Banqiao) 1.4 (about 2500 TWh/yr and 171,000 Banqiao dead) Nuclear 0.04 (5.9% of world energy) http://nextbigfuture.com/2011/03/deaths-per-twh-by-energy-source.html Risks with nuclear energy are the least
  • 10. Projected health consequences from low doses to large sections of population are questionable IN CASE OF CHERNOBYL ESTIMATED CONSEQUENCES AN ESTIMATE IN 2006—93,000 WILL DIE DUE TO CANCER UP TO THE YEAR2056 ANOTHER ESTIMATE IN 2009---985,000 DIED TILL 2004 Driven by ACTUAL CONSEQUENCE conservative linear TOTAL DEATHS; no threshold 62 (47 PLANT, 15 DUE TO THYROID CANCER ) principle (which is ACUTE RADIATION SYNDROME; not substantiated 134 (OUT OF WHICH 28 HAVE DIED) surveys in high INCREASED CANCER INCIDENCE; natural radiation AMONG RECOVERY WORKERS background areas) THYROID CANCER; (CURABLE, WAS AVOIDABLE) we tend to create 6000 ( 15 HAVE DIED) avoidable trauma in public mind
  • 11.  There is already a large used uranium fuel inventory (~270,000 tons as per WNA estimate)  While the spent fuel would be a sufficiently large energy resource if recycled, its permanent disposal is in my view an unacceptable security and safety risk (plutonium mine?)  We need to adopt ways to liquidate the spent fuel inventory through recycle  France today recycles entire spent fuel arising. Recycle is a credible option.  Development of Partitioning and Transmutation technologies can in principle effectively address long term waste management challenge. Waste management challenge can be effectively met through recycle
  • 12. The Indian Advanced Heavy Water Reactor (AHWR), a quick, safe, secure and proliferation resistant solution for the energy hungry world AHWR is a 300 MWe vertical pressure tube type, boiling light water cooled and heavy water moderated reactor (An innovative configuration that can provide low risk nuclear energy using available technologies) Major design objectives  Significant fraction of Energy from Thorium Top Tie Plate Displacer Water Rod  Several passive features Tube  3 days grace period Fuel Pin  No radiological impact AHWR can be configured to accept a  Passive shutdown system to address range of fuel types insider threat scenarios. including LEU, U-Pu , Th-Pu , LEU-Th and  Design life of 100 years. 233U-Th in full core Bottom Tie Plate  Easily replaceable coolant channels. AHWR Fuel assembly
  • 13. AHWR 300-LEU is a simple 300 MWe system fuelled with LEU-Thorium fuel, has advanced passive safety features, high degree of operator forgiving characteristics, no adverse impact in public domain, high proliferation resistance and inherent security strength. 600 Peak clad Clad temperature (K) 10 sec delay temperature hardly 590 5 sec delay rises even in the 580 2 sec delay extreme condition of complete station 570 blackout and 560 failure of primary and secondary 550 systems. 0 200 400 600 800 1000 Reactor Block Components Time (s) AHWR300-LEU provides a robust design against external as well as internal threats, including insider malevolent acts. This feature contributes to strong security of the reactor through implementation of technological solutions.
  • 14. PSA calculations for AHWR indicate practically zero probability of a serious impact in public domain Plant familiarization & Level-3 : Atmospheric Dispersion With SWS: Service identification of design Consequence Analysis Water System APWS: Active aspects important to Process Water severe accident System Release from Containment ECCS HDRBRK: ECCS Header Break PSA level-1 : Identification LLOCA: Large of significant events with Break LOCA large contribution to CDF Level-2 : Source Term (within SLOCA MSLBOB: Main Steam Line Containment) Evaluation through SWS 15% Break Outside 63% Analysis Containment Contribution to CDF Level-1, 2 & 3 PSA activity block diagram 10-10 10 -10 Frequency of Exceedence 10-11 10 -11 -12 10-12 10 10-13 10 -13 10-14 10 -14 110 mSv 0.1 Sv 1.0 Sv 10 Sv -3 -2 -1 0 10 10 10 Thyroid Dose (Sv) at 0.5 Km Iso-Dose for thyroid -200% RIH + wired shutdown Variation of dose with frequency exceedence system unavailable (Wind condition in January on western 14 (Acceptable thyroid dose for a child is 500 mSv) Indian side)
  • 15. STRONGER PROLIFERATION Amount of Plutonium in spent fuel per unit energy 30 25 Total Fissile RESISTANCE WITH AHWR 300-LEU 20 (kg/TWhe) 15 Much lower Plutonium production. 10 Plutonium in spent fuel contains lower fissile fraction, much higher 238Pu content 5 0 Modern MODERN AHWR300- AHWR300-LEU which causes heat generation & Uranium in LWR LWR LEU spent fuel contains significant 232U content which leads to hard gamma emitters. 238Pu 3.50 % 9.54 % 239Pu 51.87 % 41.65 % 240Pu 23.81 % 21.14 % The composition of the fresh as well as the 241Pu 12.91 % 13.96 % spent fuel of AHWR300-LEU makes the fuel cycle inherently proliferation resistant. 242Pu 7.91 % 13.70 % 232U 0.00 % 0.02 % Uranium in spent fuel contains about 8% 233U 0.00 % 6.51 % fissile isotopes, and hence is suitable for 234U 0.00 % 1.24 % further energy production through reuse in 235U 0.82 % 1.62 % other reactors. Further, it is also possible to 236U 0.59 % reuse the Plutonium from spent fuel in fast 3.27 % 238U 98.59 % 87.35 % reactors.
  • 16. Present deployment MOX Thorium Of nuclear power Reprocess Thermal Spent Fuel Fast Enrichment reactors Reactor Uranium LEU Plant For growth in nuclear LEU Thorium Recycle Thorium generation fuel beyond thermal reactor potential 233U Thorium LEU- Nuclear power with Thorium greater proliferation resistance Safe & Thorium Secure Reactors Reactors For ex. AHWR Recycle For ex. Acc. Driven MSR Thorium
  • 17. CHALLENGES IN SOLAR TECHNOLOGY Drive capital costs down Low cost energy storage systems Solar biomass hybrids Solar thermal photovoltaic hybrids Large solar thermal systems not dependent on availability of water Technology initiatives 1.Higher efficiency / non-toxic PV materials 2.High temperature photovoltaics 3.Self cleaning abrasion resistant surfaces 4.Recycle of Carbon-di-oxide to fluid hydrocarbon substitutes 5. ---------------
  • 18. Sustainable development of energy sector Transition to Fossil Carbon Free Energy Cycle Carbon/ ENERGY GREATER Fossil Hydrocarbons CARRIERS SHARE FOR Energy Electricity (In storage or WASTE NUCLEAR IN Resources transportation) ELECTRICITY • CO2 Electricity SUPPLY • Electricity • H2O • Fluid fuels REPLACE • Other FOSSIL Hydrogen (hydro-carbons/ oxides and HYDRO- products Sun hydrogen) CARBON IN A PROGRESSIVE MANNER CH4 Fluid Nuclear Hydro carbons RECYCLE Energy CO2 chemical CARBON- Resources Biomass reactor DIOXIDE CO2 Other DERIVE MOST recycle OF PRIMARY Nuclear Recycle modes ENERGY Sustainable Waste Management Strategies THROUGH SOLAR & Urgent need to reduce use of fossil carbon in a progressive manner NUCLEAR
  • 20. Reduced Plutonium generation High 238Pu fraction and low fissile content Amount of Plutonium in spent fuel per unit energy 30 of Plutonium Total 238Pu Fissile 239Pu 25 240Pu 241Pu 20 242Pu (kg/TWhe) 15 MODERN AHWR300-LEU LWR 238Pu 3.50 % 238Pu 9.54 % 10 239Pu 51.87 % 239Pu 41.65 % 240Pu 23.81 % 240Pu 21.14 % 5 241Pu 12.91 % 241Pu 13.96 % 242Pu 7.91 % 242Pu 13.70 % 0 MODERN AHWR300-LEU The French N4 PWR is considered as representative of a modern LWR.. The reactor has been referred from “Accelerator-driven LWR Systems (ADS) and Fast Reactor (FR) in Advanced Nuclear Fuel Cycles”, OECD (2002) STRONGER PROLIFERATION RESISTANCE WITH AHWR 300-LEU MUCH LOWER PLUTONIUM PRODUCTION Much Higher 238Pu & Lower Fissile Plutonium
  • 21. Presence of 232U in uranium from spent fuel The 232U composition 233U 234U of the fresh 235U 236U as well as the 238U AHWR300-LEU spent fuel of MODERN LWR AHWR300-LEU 232U 232U 0.02 % 0.00 % 233U 6.51 % 233U 0.00 % makes the 234U 234U 1.24 % 0.00 % 235U 0.82 % 235U 1.62 % fuel cycle 236U 236U 3.27 % 0.59 % 238U 98.59 % 238U 87.35 % inherently Uranium in the spent fuel contains about 8% fissile proliferation isotopes, and hence is suitable to be reused in other reactors. Further, it is also possible to reuse the resistant. Plutonium from spent fuel in fast reactors.