Technology options for long term nuclear power development

A. Kakodkar, Chairman, Atomic Energy Commission

1 Long term nuclear power development - The challenge of the numbers.

 A per capita electricity use of about 5000 kWh/year appears to be needed for reaching a state of reasonably high human development. Considering the progressive depletion of fossil fuel reserves, and the urgent need for addressing the global warming related concerns, nuclear energy is expected to substantially contribute to meeting the future global energy requirements.

 Assuming that at least half of the total energy demand may need to be met with nuclear, the world will need between 3000 to 4000 nuclear power reactors of different capacities for electricity generation. The number may at least double with the use of nuclear energy to provide an alternative to fluid fossil fuels.

 A large number of these reactors may need to be located in regions with high population densities and modest technological infrastructure with their sizes consistent with local needs. 2 Identified resources of uranium in once-through mode will be inadequate to support growth. 8000 IAEA INPRO GAINS High target Cases with use of 5.469 million Cumulative capacity (OT) tonne natural uranium metal 7000 Cumulative capacity (LWR-LWR (Pu-U MOX)) (Identified resources)* in LWR Cumulative capacity (LWR-LWR(Pu-Th MOX)) (OT) and LWR-MOX (both Pu- 6000 U and Pu-Th) *:Total resources (Identified 5000 + Undiscovered) are 15.969 million tonnes Ref: Uranium 2007: 4000 Demand profile as per Resources, Production and IAEA INPRO GAINS (High) Demand-The joint report by 3000 OECD Nuclear Energy By adding undiscovered Agency and the

Installed Capacity (GWe)Installed Capacity uranium resources, this International Atomic Energy 2000 Agency (RED Book 2008) point merely shifts to 2050

1000

0 1980 2000 2020 2040 2060 2080 2100 Year Uranium in open cycle is unsustainable. Recycle of in high conversion-ratio reactors has to be brought in soon enough. 3 Selection of technology options for Nuclear Reactors

Near-term  Economic competitiveness  Proven technologies

Mid/Long-term  Technology consistent with fuel cycles that (Additional support fuel resource sustainability considerations)  Enhanced levels of safety  Technological solutions to address security issues including proliferation concerns  Additional, non-power applications

Advanced Heavy Water Reactor Compact High Temperature Reactor Selection of technology options for Nuclear Fuel Cycle

Near-term  Domestic facilities/reliable supply  Economic viability  Protection of technologies Mid/Long-term  Fuel resource sustainability (Additional  Environmental sustainability through considerations) waste minimisation and disposal strategies

Cold Crucible Induction Solid Storage Melter : Engineering Surveillance Facility Reprocessing demonstration facility Plant- in-cell process piping represents at least three times larger energy resource than uranium. Its exploitation requires a proper sequencing of reactor-fuel cycle technologies in the overall programme. Important attributes of thorium 600 Example – A case study for India  Effective burner of 233 500 Pu, produces U Further growth  233U with 232U, high 400 with thorium intrinsic proliferation resistance 300 Growth with Pu-U FBRs  Lower generation of Installed capacity (GWe) (GWe) (GWe) capacity capacity capacity Installed Installed Installed 200 minor actinides Power profile  Thoria – better 100 of PHWR retention of fission programme gases, high thermal 0 1980 1995 2010 2025 2040 2055 2070 conductivity, higher Year melting point

A strategy to achieve required growth profile can be supported through timely deployment of appropriate reactor technologies including FBRs and thorium The Indian experience

7 Status of the Indian Three Stage Nuclear Power Programme

95 84 86 91 Globally Advanced 84 90 90 89 Globally Unique 90 79 85 75 72 Technology 80 69 75 World class 70 Availability 65 60 performance 55 50 1995- 1996- 1997- 1998- 1999- 2000- 2001- 2002- 2003- 2004- 2005- 96 97 98 99 00 01 02 03 04 05 06 Stage – I Stage - II Stage - III PHWRs Fast Breeder Reactors Thorium Based Reactors • 15 – Operating • 15 – Operating • 40 MWth FBTR - • 3 - Under construction • 30 kWth KAMINI- Operating • Several others planned Operating since 1985 Technology Objectives • Scaling to 700 MWe • 300 MWe AHWR- realised • Gestation period has Under Development been reduced • 500 MWe PFBR- • POWER POTENTIAL  Under Construction POWER POTENTIAL IS 10 GWe • TOTAL POWER VERY LARGE LWRs POTENTIAL  530 GWe Availability of ADS can enable • 2 BWRs Operating early introduction of Thorium (including  300 GWe with • 2 VVERs under (including 300 GWe with on a large scale construction Thorium) 8 Infrastructure for front and back end including heavy water

Uranium mining

Uranium purification through Slurry Extraction System

Gas centrifuge cascade Assembling of Pu-U Carbide Fuel Fabrication PHWR Fuel Bundles Facility (for FBTR)

Extrusion of Zirconium alloy Spent fuel storage Ingots Heavy water plant Equipment supply chain Erection of major equipment for PHWRs

End Shield Erection

Steam Generator Erection of Erection Turbo Generator Calandria Erection Construction of the PFBR: Status

Main vessel SG

 Technology with strong R&D backup  Manufacturing technology

development completed prior to start of project  Capability of Indian industries to manufacture high technology nuclear components demonstrated (main vessel, safety vessel, steam generator, grid plate) PFBR will be commissioned by Sept 2010 Inspection, maintenance and replacement of major equipment and components

Mock-up Pump set INGRES-2S

INGRES-3S Manipulator INGRES-4S Access Control to tubes panel Sludge lancing equipment

BARCIS

NIVDT

Tools for life management Replacement of Steam Generator- of coolant channels Hair pin heat exchanger in MAPS En-Masse Coolant Channel Replacement Competitive economics of Indian reactors

Indian Global range PHWRs (700 MWe) TAPS 1&2 Tariffs at 2008$s Capital Cost 1700* 2000-2500 $/kWe $/kWe

Construction 5-6 years 5-6 years 35 period

UEC $/MWh 60 60 - 70 30

25 Capital Cost of recently completed 2008$/MW h units 20 TAPS – 3 & 4 Rs. 58850* million (540 MWe) ~ 1200* $/kWe 15 Kaiga – 3&4 Rs. 26000* million (220 MWe) ~ 1300* $/kWe * Cost figures pertain to the Indian domestic context. In the 1988 1991 1994 1997 2000 2003 2006 international context these figures will be location dependent. The Indian Advanced Heavy Water Reactor (AHWR) AHWR is a 300 MWe vertical pressure tube type, boiling light water cooled and heavy water moderated reactor using 233U-Th MOX and Pu-Th MOX fuel.

Major design objectives

 65% of power from Th

Top Tie Plate  Several passive features Displacer  3 days grace period Water Rod Tube  No radiological impact Fuel Pin

 Passive shutdown system to address insider threat AHWR can be configured to scenarios. accept a range of fuel types including enriched U, U-Pu  Design life of 100 years. MOX, Th-Pu MOX, and 233U-Th MOX in full core Bottom Tie Plate  Easily replaceable coolant AHWR Fuel channels. assembly 16 Minor actinide production in the Pu-Th and the 233U-Th bearing pins of fuel used in the current design of AHWR

18

16

Central 14 Pu-Th MOX pins Structural tube 12

233U-Th 10 Water MOX pins

8

6

4 Minor Actinide produced (g/GWd) produced Actinide Minor 2

0 233U-Th Pins Pu-Th Pins

17 Transients following station black-out and failure of wired shut-down systems 700 Clad Surface Temperature

10 sec delay Peak clad 650 5 sec delay temperature hardly 2 sec delay rises even in the extreme condition of complete station 600 blackout and failure of primary and secondary shutdown systems.

Clad Temperature (K) 550

500 0 200 400 600 800 1000 Time (s)

18 Conclusion (1/2)

 Globally, the technology options for long-term nuclear power development need to be based on a scientific approach to attain sustainability of nuclear fuel resources and environment even while addressing, enhanced global reach and volume of deployment of nuclear energy.

 Similarly, concerns relating to safety, security and proliferation issues also need to be handled through technological means. This, perhaps, is the only way for sustainable management of these issues.

 The Indian nuclear programme is consistent with the above objectives. Conclusion (2/2)

 At present, India has robust technologies in all aspects of nuclear energy.

 India is operating the world’s smallest power reactors. The performance of these reactors is competitive with the larger sized reactors inspite of the latter having the benefit of economics of scale.

 The Indian industry has adequate resources and expertise and India can become a manufacturing hub for the nuclear industry. This could include not only reactors but also supply of fuel. Thank you for your attention.