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AHWR300-LEU
              Lowering threats
               in sustainable
                development
                using nuclear
                   energy



                   Anil Kakodkar
Per capita
                                          el.
                                                  consumption
                                          kWh
                                                         (HDI)
                                          Goa         2263
                                                      (0.792)
               HDI unaffected by change
               in electricity use         Bihar        122
                                                      (0.542)

                                          All India    779
HDI strongly                                           (0.605)
dependent on
electricity
use
World        OECD          World-OECD
Population
(billions)            6.7          1.18                 5.52

Annual
Electricity
Generation           18.8           10.6                8.2
(trillion kWh)

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

Annual
av. per capita       ~2800          ~9000              ~1500
Electricity (kWh)

Additional annual electricity generation needed just to reach
5000kWh average per-capita electricity (necessary for a reasonable
standard of living) in non-OECD countries would amount to ~20
trillion kWh that is roughly equal to present total generation.
THE CRUCIAL ENERGY
     CHALLENGE
World electricity supply would need to nearly
double (around 3000 GWe additional electric
generation capacity) just to support a reasonable
standard of living for all
Timely ability to cater to this need in a
sustainable manner(or at least reserve equitable
resources for the purpose) is in my view a
prerequisite for long term peace and stability
On the other hand the threat of climate change
requires reduction in use of fossil energy
Clearly business as usual approach will not do
and nuclear energy has to play much greater role
A much              Experience has
                                   IS THERE ENOUGH URANIUM ?                                                talked
                                                                                                          about view
                                                                                                                                  shown that
                                                                                                                                investment in
         Cumulative uranium              low proj-3.4 million tons                                                              exploration is
                                                                                                                                   driven by
         demand by 2050               middle proj-5.4 million tons                                                               demand and
         (Analysis of uranium supply high proj-7.6 million tons                                                                   prices. No
         to 2050-IAEA publication)                                                                                                shortage is
                                                                                                                                   foreseen
         Jan2009 estimate of uranium at 6.3 million tons
         (includes U up to $ 260/Kg). Should last a 100 years
         at 2008 consumption rate                Cases with use of 5.469 million tonne natural uranium
                                                                                             metal (Identified resources)* in LWR (OT) and LWR-MOX
                           8000
                                         IAEA INPRO GAINS High target
                                                                                             (both Pu-U and Pu-Th)
                                         Cumulative capacity (OT)                            *:Total resources (Identified + Undiscovered) are 15.969
                           7000          Cumulative capacity (LWR-LWR (Pu-U MOX))            million tonnes
                                         Cumulative capacity (LWR-LWR(Pu-Th MOX))
                                                                                             Ref: Uranium 2007: Resources, Production and
Installed Capacity (GWe)




                           6000
                                                                                             Demand-The joint report by OECD Nuclear Energy
                           5000
                                                                                             Agency and the International Atomic Energy Agency
                                     Demand profile as per                                   (RED Book 2008)
                           4000      IAEA INPRO GAINS (High)                                 Uranium in open cycle is unsustainable
                                  By adding undiscovered                                     if nuclear energy is to meet a
                           3000
                                  uranium resources, this                                    reasonable fraction of carbon free
                                  point merely shifts to 2050                                electricity requirements.
                           2000


                           1000                                                              Recycle of nuclear fuel in breeder
                                                                                             reactors has to be brought in soon
                             0                                                               enough
                                  1980       2000    2020      2040    2060    2080   2100
                                                            Year                                                                                    5
Recycle of nuclear fuel is also necessary to resolve the
         issue of permanent disposal of spent fuel
 There is already a large used uranium fuel inventory (~270,000 tons as
  per WNA estimate). Its permanent disposal has remained an
  unresolved issue which in my view is unlikely to be resolved.


 While the spent fuel would be a sufficiently large energy resource if
  recycled, its permanent disposal ( if resorted to ) 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


 While direct disposal of spent fuel is a long term risk, universal
  adoption of recycle is not likely to gain ground on account of nuclear
  security concerns
Risk
    Nuclear Security                         Climate Change

    #Diversion of nuclear materials for      # Difficult to predict global
    weapons purposes – Could cause           consequences – Could well be much
    threat any where                         larger that what can be caused by
                                             WMDs
    #Threat to nuclear facility can cause
    public trauma– Threat primarily in       # Development deficit and varying
    the neighborhood of the facility         energy security challenges



Minimisation of risk to humanity would necessitate rapid growth of
nuclear power.

Security measures alone, though necessary, are unlikely to be
sufficient. Sovereignty of nations, varying degree of security deficit,
responsible behaviour & trust deficit, managing non-state actors etc.
are likely to remain difficult challenges.

Technology measures that provide inherent proliferation resistance
and security strength must be quickly brought in to replace fossil
energy.
Thorium, a one stop solution to safety, sustainability
              and proliferation resistance
                                                                           Options for plutonium disposition
                            80                                            – Uranium-based       fuel:   Neutron
                                                Initial fuel                absorption in 238U generates
                                                                            additional plutonium.
Fissile plutonium content




                            60
    in the fuel (kg/te)




                                                                          – Inert matrix fuel (non-fertile metal
                            40                                              alloys containing Pu): Degraded
                                                                            reactor kinetics - only a part of the
                            20                                              core can be loaded with such a
                                           Discharge fuel                   fuel, reducing the plutonium
                             0
                                 0   20    40       60         80   100
                                                                            disposition rate.
                                     Discharge burnup (GWd/te)            – Thorium: Enables more effective
                            Plutonium destruction in thorium-               utilisation of Pu, added initially,
                            plutonium fuel in PHWR                          while     maintaining     acceptable
                                                                            performance characteristics.
Detectability of 233U (contaminated with 232U) for
                                     all the cases, is unquestionable
                                                                          16
                            6000                                                                                                 6000                                      1000
                                            233
                                                 U                        14                                                                Exposure




                                                                                                                                                                                                  U
                            5000                                                                                                 5000
                                                                          12                                                                time for           U
                                                                                                                                                             232




                                                                                                                                                                                                         332
                            4000                     232
                                                          U               10                                                     4000       lethal dose                    100

                            3000                                          8                                                      3000
                                                                          6
                            2000                                                                                                 2000                                      10
                                                                          4
                            1000                                          2                                                      1000
                               0                                           0


                                                                               no t art nec n32c U
                                                                                                                                   0                                        1




                                                                                                                                                                                                              f D 0a
                                   0   20   40       60       80   100   120




                                                                                                                                                                                                    gk 4 8 r o m1 t 5
                                                                                                                                        0     20   40   60     80   100   120


                                                                               ) MHf o gk/ g(

                                                                                                     m p n no t art nec n32c U
                                                                                            3o
m p n no t art nec n32c U




                                                                                                                                                                                 eri uqc a o )r h( e m er us opx E
                                                                                                                                                                                                                 L
                                   Burnup GWd/te                                                                                            Burnup GWd/te


                                                                                                                        2o
                   2o




                                                                                 i




                                                                                                                                                                                                        .
                                                                                                                                                                                                     it
                                                                                                            i
       i




                                                          Case of Pu-RG+Thoria in AHWR
                                                                                                      p i
 p i




                                                                                                                                                                                            t
The Indian Advanced Heavy Water Reactor (AHWR),              a
   quicker 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
   range of fuel types               address insider threat scenarios.
   including LEU, U-
   Pu , Th-Pu , LEU-Th              Design life of 100 years.
   and 233U-Th in full                                                         Bottom Tie Plate
   core                             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.
                                   Peak clad
                             temperature hardly
                               rises even in the
                              extreme condition
                             of complete station
                                 blackout and
                              failure of primary
                                and secondary
                                   systems.
  Reactor Block Components

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.
Presence of 232U in uranium from spent fuel
                                                                           The
                                                                 232
                                                                    U
                                                                 233
                                                                     U     composition
                                                                 234
                                                                       U
                                                                 235
                                                                     U     of the fresh (LEU
                                                                 236
                                                                     U     in Thorium)
                                                                 238
                                                                     U
                                                                           as well as the

              MODERN                           AHWR300-LEU
                                                                           spent fuel of
               LWR

                                           U      0.02       %             AHWR300-LEU
    232
          U      0.00     %          232


    233
          U      0.00     %          233
                                           U      6.51       %             makes the
    234
          U      0.00     %          234
                                           U      1.24       %
                                                                           fuel cycle
    235
          U      0.82     %          235
                                           U      1.62       %
    236
          U      0.59     %          236
                                           U      3.27       %             inherently
    238
          U      98.59    %          238
                                           U      87.35      %
                                                                           proliferation
Uranium in the spent fuel contains about 8% fissile isotopes,              resistant.
and hence is suitable to be reused in other reactors. Further, it
is also possible to reuse the Plutonium from spent fuel in fast
reactors.
Reduced Plutonium generation                  High 238Pu fraction and low fissile content of
                                                                Plutonium
                                                                                                                                                      238
                                                                                                                                                         Pu
                                                                                                                                                      239
                                                                                                                                                         Pu
                                                                                                                                                       240
                                                                                                                                                             Pu
                                                                                                                                                       241
                                                                                                                                                             Pu
                                                                                                                                                       242
                                                                                                                                                             Pu


                                                         MODERN                                              AHWR300-LEU
                                                          LWR
                                        238
                                              Pu              3.50                %                  238
                                                                                                           Pu              9.54                %
                                        239
                                              Pu              51.87               %                  239
                                                                                                           Pu              41.65               %
                                        240
                                              Pu              23.81               %                  240
                                                                                                           Pu              21.14               %
                                        241
                                              Pu              12.91               %                  241
                                                                                                           Pu              13.96               %
                                        242
                                              Pu              7.91                %                  242
                                                                                                           Pu              13.70               %
                               The French N4 PWR is considered as representative of a modern LWR.. The reactor has been referred from “Accelerator-driven 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
AHWR300-LEU
                            provides a better
                            utilisation of
                            natural uranium,
                            as a result of
                            a significant
                            fraction of the
                            energy is extracted
                            by fission of 233U,
                            converted in-situ
                            from the thorium
                            fertile host.


      With high burn up possible today,
LEU-Thorium fuel can lead to better/comparable
         utilisation of mined Uranium
Thorium thus offers the potential
for a wider deployment of nuclear
power with reduced threats ( both
nuclear as well as those related
to climate change )
“IAEA is not concerned with the tenth or the
thousandth nuclear device of a country. IAEA is only
concened with the first.

- And that will certainly not be based on a thorium
  fuel cycle”
   - ---------Bruno
   -Bruno Pellaud, Former Deputy Director General,IAEA



                                                         16
While greater geographical spread of nuclear
energy with minimised risk can be realised by
Thorium-LEU fuel, there would still be a
question of meeting energy needs beyond
what can be supported by thermal reactors

Fast breeder reactors would thus be
necessary for growth in nuclear power
capacity beyond thermal reactor potential

Fast reactors as well as uranium fuel
enrichment and recycle would however need
to be kept within a more “responsible”
domain
Present deployment                                           MO                   Thorium
                                                              X
 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                                    U
                                                                                     233

                                                                                   Thorium
   LEU-
                                  Nuclear power with
 Thorium                         greater proliferation
                                       resistance

             Safe &                                                   Thorium
             Secure
            Reactors                                                  Reactors
           For ex. AHWR                   Recycle                     For ex. Acc.
                                                                      Driven MSR

                                                            Thorium
Thank
 you

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Lowering threats in sustainable development using nuclear energy

  • 1. AHWR300-LEU Lowering threats in sustainable development using nuclear energy Anil Kakodkar
  • 2. Per capita el. consumption kWh (HDI) Goa 2263 (0.792) HDI unaffected by change in electricity use Bihar 122 (0.542) All India 779 HDI strongly (0.605) dependent on electricity use
  • 3. World OECD World-OECD Population (billions) 6.7 1.18 5.52 Annual Electricity Generation 18.8 10.6 8.2 (trillion kWh) Carbon-di-oxide Emission 30 13 17 (billion tons/yr) Annual av. per capita ~2800 ~9000 ~1500 Electricity (kWh) Additional annual electricity generation needed just to reach 5000kWh average per-capita electricity (necessary for a reasonable standard of living) in non-OECD countries would amount to ~20 trillion kWh that is roughly equal to present total generation.
  • 4. THE CRUCIAL ENERGY CHALLENGE World electricity supply would need to nearly double (around 3000 GWe additional electric generation capacity) just to support a reasonable standard of living for all Timely ability to cater to this need in a sustainable manner(or at least reserve equitable resources for the purpose) is in my view a prerequisite for long term peace and stability On the other hand the threat of climate change requires reduction in use of fossil energy Clearly business as usual approach will not do and nuclear energy has to play much greater role
  • 5. A much Experience has IS THERE ENOUGH URANIUM ? talked about view shown that investment in Cumulative uranium low proj-3.4 million tons exploration is driven by demand by 2050 middle proj-5.4 million tons demand and (Analysis of uranium supply high proj-7.6 million tons prices. No to 2050-IAEA publication) shortage is foreseen Jan2009 estimate of uranium at 6.3 million tons (includes U up to $ 260/Kg). Should last a 100 years at 2008 consumption rate Cases with use of 5.469 million tonne natural uranium metal (Identified resources)* in LWR (OT) and LWR-MOX 8000 IAEA INPRO GAINS High target (both Pu-U and Pu-Th) Cumulative capacity (OT) *:Total resources (Identified + Undiscovered) are 15.969 7000 Cumulative capacity (LWR-LWR (Pu-U MOX)) million tonnes Cumulative capacity (LWR-LWR(Pu-Th MOX)) Ref: Uranium 2007: Resources, Production and Installed Capacity (GWe) 6000 Demand-The joint report by OECD Nuclear Energy 5000 Agency and the International Atomic Energy Agency Demand profile as per (RED Book 2008) 4000 IAEA INPRO GAINS (High) Uranium in open cycle is unsustainable By adding undiscovered if nuclear energy is to meet a 3000 uranium resources, this reasonable fraction of carbon free point merely shifts to 2050 electricity requirements. 2000 1000 Recycle of nuclear fuel in breeder reactors has to be brought in soon 0 enough 1980 2000 2020 2040 2060 2080 2100 Year 5
  • 6. Recycle of nuclear fuel is also necessary to resolve the issue of permanent disposal of spent fuel  There is already a large used uranium fuel inventory (~270,000 tons as per WNA estimate). Its permanent disposal has remained an unresolved issue which in my view is unlikely to be resolved.  While the spent fuel would be a sufficiently large energy resource if recycled, its permanent disposal ( if resorted to ) 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  While direct disposal of spent fuel is a long term risk, universal adoption of recycle is not likely to gain ground on account of nuclear security concerns
  • 7. Risk Nuclear Security Climate Change #Diversion of nuclear materials for # Difficult to predict global weapons purposes – Could cause consequences – Could well be much threat any where larger that what can be caused by WMDs #Threat to nuclear facility can cause public trauma– Threat primarily in # Development deficit and varying the neighborhood of the facility energy security challenges Minimisation of risk to humanity would necessitate rapid growth of nuclear power. Security measures alone, though necessary, are unlikely to be sufficient. Sovereignty of nations, varying degree of security deficit, responsible behaviour & trust deficit, managing non-state actors etc. are likely to remain difficult challenges. Technology measures that provide inherent proliferation resistance and security strength must be quickly brought in to replace fossil energy.
  • 8. Thorium, a one stop solution to safety, sustainability and proliferation resistance Options for plutonium disposition 80 – Uranium-based fuel: Neutron Initial fuel absorption in 238U generates additional plutonium. Fissile plutonium content 60 in the fuel (kg/te) – Inert matrix fuel (non-fertile metal 40 alloys containing Pu): Degraded reactor kinetics - only a part of the 20 core can be loaded with such a Discharge fuel fuel, reducing the plutonium 0 0 20 40 60 80 100 disposition rate. Discharge burnup (GWd/te) – Thorium: Enables more effective Plutonium destruction in thorium- utilisation of Pu, added initially, plutonium fuel in PHWR while maintaining acceptable performance characteristics.
  • 9. Detectability of 233U (contaminated with 232U) for all the cases, is unquestionable 16 6000 6000 1000 233 U 14 Exposure U 5000 5000 12 time for U 232 332 4000 232 U 10 4000 lethal dose 100 3000 8 3000 6 2000 2000 10 4 1000 2 1000 0 0 no t art nec n32c U 0 1 f D 0a 0 20 40 60 80 100 120 gk 4 8 r o m1 t 5 0 20 40 60 80 100 120 ) MHf o gk/ g( m p n no t art nec n32c U 3o m p n no t art nec n32c U eri uqc a o )r h( e m er us opx E L Burnup GWd/te Burnup GWd/te 2o 2o i . it i i Case of Pu-RG+Thoria in AHWR p i p i t
  • 10. The Indian Advanced Heavy Water Reactor (AHWR), a quicker 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 range of fuel types address insider threat scenarios. including LEU, U- Pu , Th-Pu , LEU-Th  Design life of 100 years. and 233U-Th in full Bottom Tie Plate core  Easily replaceable coolant channels. AHWR Fuel assembly
  • 11. 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. Peak clad temperature hardly rises even in the extreme condition of complete station blackout and failure of primary and secondary systems. Reactor Block Components 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.
  • 12. Presence of 232U in uranium from spent fuel The 232 U 233 U composition 234 U 235 U of the fresh (LEU 236 U in Thorium) 238 U as well as the MODERN AHWR300-LEU spent fuel of LWR U 0.02 % AHWR300-LEU 232 U 0.00 % 232 233 U 0.00 % 233 U 6.51 % makes the 234 U 0.00 % 234 U 1.24 % fuel cycle 235 U 0.82 % 235 U 1.62 % 236 U 0.59 % 236 U 3.27 % inherently 238 U 98.59 % 238 U 87.35 % proliferation Uranium in the spent fuel contains about 8% fissile isotopes, resistant. and hence is suitable to be reused in other reactors. Further, it is also possible to reuse the Plutonium from spent fuel in fast reactors.
  • 13. Reduced Plutonium generation High 238Pu fraction and low fissile content of Plutonium 238 Pu 239 Pu 240 Pu 241 Pu 242 Pu MODERN AHWR300-LEU LWR 238 Pu 3.50 % 238 Pu 9.54 % 239 Pu 51.87 % 239 Pu 41.65 % 240 Pu 23.81 % 240 Pu 21.14 % 241 Pu 12.91 % 241 Pu 13.96 % 242 Pu 7.91 % 242 Pu 13.70 % The French N4 PWR is considered as representative of a modern LWR.. The reactor has been referred from “Accelerator-driven 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
  • 14. AHWR300-LEU provides a better utilisation of natural uranium, as a result of a significant fraction of the energy is extracted by fission of 233U, converted in-situ from the thorium fertile host. With high burn up possible today, LEU-Thorium fuel can lead to better/comparable utilisation of mined Uranium
  • 15. Thorium thus offers the potential for a wider deployment of nuclear power with reduced threats ( both nuclear as well as those related to climate change )
  • 16. “IAEA is not concerned with the tenth or the thousandth nuclear device of a country. IAEA is only concened with the first. - And that will certainly not be based on a thorium fuel cycle” - ---------Bruno -Bruno Pellaud, Former Deputy Director General,IAEA 16
  • 17. While greater geographical spread of nuclear energy with minimised risk can be realised by Thorium-LEU fuel, there would still be a question of meeting energy needs beyond what can be supported by thermal reactors Fast breeder reactors would thus be necessary for growth in nuclear power capacity beyond thermal reactor potential Fast reactors as well as uranium fuel enrichment and recycle would however need to be kept within a more “responsible” domain
  • 18. Present deployment MO Thorium X 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 U 233 Thorium LEU- Nuclear power with Thorium greater proliferation resistance Safe & Thorium Secure Reactors Reactors For ex. AHWR Recycle For ex. Acc. Driven MSR Thorium