1. Prospect of Nuclear Energy in India
Prospect of Nuclear Energy in India
DEB MUKHOPADHYAY
Sustainable Lifestyle = Positive Climate Action

2. Electricity Generation Scenario in India
All India Installed Capacity (MWe) as on September 2016
• At present India is ranked 5th in world in installed capacity and generation
A shortfall of 10-12% remains during peak time to meet the GDP growth projection
There is an urgent need to enhance power generation in the country without increase in the carbon emission
Note: Captive Genaration is not included in the total
Source: Executive Summary for the Month of Sept, 2016, Central Electricity Authority New Delhi, India

3. Nuclear Power for Sustainable supply of Energy- Indian Scenario
Nuclear Power for Sustainable
supply of Energy- Indian Scenario
• 8-9% growth requires GW capacity by 2032
3-4 billion tonnnes of CO2 emission expected from fossil fuel used to meet the balance requirement
• Renewable, Hydro and Nuclear Power are options for clean energy
Nuclear program aims for 20.0 GWe by 2024
[Strategy for growth of Electricity in India, Primary Energyhttp://
Source: Integrated Energy Policies, Report of the
expert committee, Planning Commission 2006

4. Indian Nuclear Power Program
The program is based on the reserves of Uranium (~61,000 tonnes) and large reserves of Thorium (~ 2,25,000 tonnes)
Limited U resources and large Th resources lead to adoption
of closed fuel cycle policy in the program to utilise the
available resources to a best possible way
3-Stage Nuclear Power Program:
Stage 1: Use of Natural uranium in PHWR
Stage 2: Fast Breeder reactors using reprocessed Pu from
Thermal Reactors and Thorium Blankets
Stage 3: Thorium-Uranium 233 reactors
Source: A strategy for growth of electrical energy in India, Department of Atomic Energy and
Natural Uranium deposits - ~70,000 tonnes 
Thorium deposits - ~ 3,60,000 tonnes

5. Indian Nuclear Power Program
Indian Nuclear Power Program
The goal of three stage Indian nuclear power programme is longterm
resource sustainability

6. Indian Nuclear Power Program
Stage-I: Natural Uranium based PHWRs
Projected Installation upto 2055: 7.26 Gwe
Stage-II: Fast Breeder Reactors using re-processed Pu and at a later stage Th in the blanket and Metallic Fuel
Projected Installation upto 2055: 200 GWe
Stage-III: Self sustaining Th-U233 based reactors
Results of a case study; assumptions te Uranium and short doubling time FBRs beyond 2021

7. Indian Nuclear Power Program
Indian Nuclear Power Program
Stage-I:
PHWRs : 18 operating (4460 MWe), 4 units of 700 Mwe under construction (2800 MWe) and 48 units planned
LWRs: 2 BWRs Operating (320 MWe) and 2 VVERs Operating (2000 MWe). 2 more units of VVER (1000 MWe each) are planned
Stage-II: Pu Cycle
FBRs : One 40 MWth operating since 1985, 500 MWe PFBR under comissioning and two FBR units designed
Stage-III: Thorium Cycle
One 30 KWth KAMINI operating and 300 MWe Thorium based AHWR is ready for deployment.

8. PHWR Technology –Stage I
PHWR Technology –Stage I
Performance & Economics of Indian PHWR based NPPs
Capital cost for construction is substantially lower as compared to world average
Minimisation of construction period has helped to minimise the cost
A lower Unit Energy Cost (UEC) is achieved as compared to global range
An overall better capacity factor is achieved which helped to lower down the overall UEC

9. PHWR Technology Evolution –Stage I
Major Components of PHWR: Industry Participation
Primary Side:
Reactor Channels
and Fuel Bundles
Calandria Vessel
Steam Generators
Circulating Pumps
Headers
Fuelling Machine
Secondary Side
Turbines
Deaerator
Condensor
Pumps
Containment
Calandria
Fuel Bundle
PHWR Nuclear Containment
F/M Head
Steam Generator

10. PHWR Technology Enhancement -Stage I
Post Fukushima Safety Enhancement
Enhancing Severe Accident management Program
Station specific accident management guidelines
Hookup provisions for core cooling
Solar lighting
Strengthening hydrogen management provisions
Indigenous Passive Catalytic Recombiner Device (PCRD) development and testing
Additional provision of removal of fission product
Indigenous Containment Filtered Venting System (CFVS) Development and testing
Creation of on-site emergency support centre
Additional safety features for new designs
Passive Decay Heat Removal System, Melt Retention, Core Catcher
Hook up arrangements
PCRD test Facility
CFVS Component

11. LWR Program & Safety Enhancement –Stage I
LWR Program & Safety Enhancement –Stage I
Operating LWRs based on foreign technical cooperation
GE- BWR (TAPS-1&2): Installation of additional DGs etc.
VVER 1000 (KK-1): Ultimate Heat Sink
(Air cooled PHRS)
Planned LWRs based on foreign technical cooperation
VVER
AP1000
EPR
Indian PWR (IPWR) technology development Program for 900 MWe, a joint project of BARC & NPCIL
Indian industry is poised to make heavy and critical equipment like Reactor Pressure Vessel (RPV), steam generators (SG), PHT Pumps, etc.

12. Front end of Nuclear Fuel Cycle - Stage I
Front end of Nuclear Fuel Cycle - Stage I
The Nuclear Fuel Complex (NFC)was established in the early 70s.
Making nuclear fuel assemblies and core structural components for the entire nuclear power programme of the country. 
Processing of uranium ore concentrate and zircon sand through a series of indigenously developed chemical and metallurgical operations. 
Making seamless tubes by hot extrusion and cold pilgering process.
the NFC has also ventured recently into export of some of its products like zirconium bars and anhydrous magnesium chloride. 

13. Fuel Cycle & Sustainability
Fuel Cycle & Sustainability
Reprocessing of spent fuel :
A closed cycle for long term energy is envisaged in view of phased expansion for second and third stages
Indigenous technology for reprocessing of the spent fuel is developed
Waste management programme has been developed by its own comprehensive R&D efforts and reprocessing plants were set up and are in operation thereby attaining self reliance
Vitrification facility
Vitrified Waste Storage facility

14. Fuel Reprocessing Cycle & Sustainability
Fuel Reprocessing Cycle & Sustainability
Reprocessing of Spent fuel : PUREX
Open Cycle:
Disposal of the entire waste after subjecting to proper waste treatment
Closed cycle:
Separation of U-238 and Pu-239
Further recycled for other radioactive FP separation for useful purposes like production of Cs-137 pencils for medical purposes
Appropriately disposed off with minimum environmental disturbance.
Indian Nuclear Fuel Cycle: Today
resulting huge underutilization of the energy potential of Uranium (~ 2 % is exploited)

15. PFBR Technology – Stage II
PFBR Technology – Stage II
Proto Type Fast Breeder Reactor (PFBR) –Under Commissioning
Fuel : PuO2 + UO2
Electrical output : 500/470 MWe
Coolant : Sodium
Gross thermal Efficiency : 40%
Economy
Reactor Vessel

16. PFBR Indigenous Technology – Stage II
PFBR Indigenous Technology – Stage II
Proto Type Fast Breeder Reactor (PFBR) –Industry Participation
Main vessel
Safety vessel
Steam generator
Roof slab
Sodium & argon buffer storage tanks
Metal reflective thermal insulation panels
Inclined fuel transfer arm
Boron carbide shielding structure
Dummy fuel blanket sub-assemblies

17. Thorium Technology –Stage III
A Road Map for Deployment of Thorium Based Reactors
Based on the study premature large scale deployment of thorium leads to sub-optimal use of indigenous energy resource
Incorporation of thorium in the blankets of metallic fuelled fast breeder reactors – after significant FBR capacity built-up
Necessary to build-up a significant level of fissile material before
launching thorium cycle in a big way for the third stage
Thorium based reactors expected to be deployed largely beyond 2070
AHWR – Thorium fuel cycle demonstrator by 2026
Surplus U-233 formed in future FBRs could drive HTRs programme including MSBRs

18. Thorium Technology –Stage III
Advantages of Thoria Cycle:
ThO2 - Physical and Chemical Properties
Relatively inert as compared to UO2.
Does not react with water.
Higher thermal conductivity than UO2.
Lower co-efficient of thermal expansion than UO2.
Higher Melting point than UO2
Fission gas release rate one order of magnitude lower than that of UO2.
Good radiation resistance and dimensional stability
Radiation Stability
Study
ThO2-4% PuO2
UO2-4% PuO2

19. Thorium Technology –Stage III
Advantages of Thoria Cycle:
Important Neutronic Characteristics
Intrinsic Barrier to Proliferation
η value for U233 remains nearly constant
Helps of high conversion ratios with thorium utilisation
U232 and U233 is formed from Th232
The half-life of U232 is about 69 years.
The daughter products Tl and Bi are high energy gamma emitting isotopes.
Presence of U232 in separated U233, offers good proliferation-resistant characteristics.

20. Introduction of Thorium Technology –Stage III
Evolution of thorium fuel cycle development
Thoria Irradiation in Indian reactors
Irradiation of (Th-Pu)O2
in research reactors
Thoria bundles irradiated
in the blanket zone of
Fast Breeder Test Reactor
(FBTR)
232 Thorium bundle
irradiation in PHWRs
with 14,000 MWd/Te

21. Thorium Fuel Fabrication –Stage III
Experience with fabrication of thoria-based fuel
Thoria bundles for PHWRs
Thoria assemblies for research reactor irradiation
(Th-Pu) MOX pins for test irradiations
Thoria microspheres and ThO2 Pellets
fabricated for AHWR Critical Facility
Thorium fuel cycle technologies is relatively
complex because of inert nature of thoria
radiological aspects
MOX Powder Processing

22. Thorium Technology Demonstrator- Stage III
Thorium Technology Demonstrator- Stage III
Advanced Heavy Water Reactor (AHWR) –Ready for launching
AHWR is a 300 MWe, vertical, pressure tube
type, boiling light water cooled, and
heavy water moderated reactor
AHWR is a technology demonstration reactor,
designed to achieve large-scale use of thorium
for power generation
Provides transition to 3rd stage of the Indian
Nuclear Power Programme.
Addresses most issues relevant to advanced reactor designs like sustainability, enhanced safety, proliferation resistance and economic competitiveness.
Number of passive safety features to reduce environmental impact.
Fuel cycle flexibility

23. Thorium Technology - Stage III
Thorium Technology - Stage III
Advanced Heavy Water Reactor (AHWR) –Passive Cooling for Strengthening Defense-in-Depth Approach
Passive Core Cooling by Natural Circulation
Passive decay heat removal by Condenser
Passive Shutdown System
Passive Emergency Core Cooling
Injection by Accumulator and GDWP
Passive Containment Coolers
Project Status:
Design Validation is done through extensive experimental program
Pre-licensing safety appraisal by AERB
Site selection is in progress

24. Thorium Technology for Advanced Reactor Programme - Stage III
Thorium Technology for Advanced Reactor
Programme - Stage III
Technology development programs are launched for Thorium utilization
High Temperature Reactor Program
Compact High Temperature Reactor (CHTR)
Indian High Temperature Reactor (IHTR)
Indian Molten Salt Breeder Reactor (MSBR)
Reasons for pursuing high temperature reactor program
Higher thermal efficiency
Hydrogen generation as a combustible fuel
Low minor actinide generation –easy to handle for reprocessing
Proliferation resistance
H2 Generation

25. Thorium Technology - Stage III
Thorium Technology - Stage III
Indian High Temperature Reactor Program
CHTR-Technology Demonstrator
100 kWth, 1000 °C, TRISO fuel
passive systems for reactor heat removal
Prolonged operation without refuelling
IHTR-for Hydrogen Production
600 MWth, 1000 °C, TRISO fuel
Active & passive control & cooling
On-line refuelling
MSBR
Medium power, moderate temperature
Reactor based on U233-Th fuel cycle

26. Thorium Technology - Stage III
Thorium Technology - Stage III
R&D Program for High Temperature Reactor Program:
High packing density fuel compacts based on TRISO coated particle fuel
Materials for fuel tube, moderator
and reflector
Carbon based materials (graphite and carbon carbon composite)
Beryllia
Graphite
Oxidation & corrosion resistant coating
Heat pipes

27. Thorium Technology - Stage III
Thorium Technology - Stage III
R&D Program for High Temperature Reactor Program:
Metallic structural materials
Nb-1%Zr-0.1%C alloy, Ta alloy
Thermal hydraulics Studies for
LBE coolant
Molten Salt Coolant
Kilo Temperature Loop (KTL)
Molten Salt Corrosion Study

28. Thorium Technology - Stage III
Thorium Technology - Stage III
Major Challenges in Development of High Temperature Reactor
Material development for high temperature reactors
Remote handling
Fuel reprocessing due to high gamma daughter products
Nuclear Data
Appropriate computational analysis tool for Thermal-Hydraulics and Neutronic coupled simulation for Molten Salt Breeder Reactor
On-line fission product removal techniques for Molten Salt Breeder Reactor
Natural circulation based reactors stability

29. PRESENTATION SUMMARY INDIA@COP22
India’s 3 stage Nuclear Power Program is planned to achieve a sustained energy production by effective utilization of both fissile & fertile elements, thus aim to reduce carbon emission
The Nuclear Program of Stage-I and Stage-II are matured and growing
Advancements on better fuel utilization, higher energy conversion and reduction of activity levels in radio-active waste are pursued rigorously.
Foreign Reactors based NPPs are making it’s way to boost the Energy Growth in Nuclear Based Power in India
The Stage-III Program is evolving with Thorium utilization concept and Advance Heavy Reactor is readied for construction
Technologies for thorium utilizations namely High Temperature Reactors under Stage-III Program are on-going for power and hydrogen generation and extensive R&D program is in place to overcome the technological challenges

30.
Thanks for your
kind attention!!