1. An overview of nuclear reactor facilities in India
Umasankari Kannan
Reactor Physics Design Division
Bhabha atomic Research Centre
IWAAP th Nov 2017 Mumbai

2. Outline of the talk Introduction Brief overview of Research Reactors
India’s nuclear programme
The Indian scenario
Brief overview of Research Reactors
Dhruva, NRF-N
FBTR
KAMINI
BRAHMMA
Power reactors
PHWR, BWR, VVER, PFBR
Future reactors
Advanced Heavy Water Reactor (AHWR)
Indian Pressurised Water Reactor (IPWR)
Compact High Temperature Reactor (CHTR)
Some simulation and experimental results
Neutron spectrum
Fissile fraction
IWAAP th Nov 2017 Mumbai

3. The Indian nuclear power programme
IWAAP th Nov 2017 Mumbai

4. Three Stage Nuclear Power Programme- Present Status
Stage - II
Fast Breeder Reactors
40 MWth FBTR - Operating since 1985,
Technology Objectives realized.
500 MWe PFBR-
To be commissioned
Stage-II POWER POTENTIAL :  530,000 Mwe
Stage – I PHWRs
18 - Operating
Scaling to 700 MWe
56- Under construction
Gestation period has been reduced
POWER POTENTIAL  10,000 MWe
LWRs
2 BWRs Operating
2 VVERs operating
Stage - III
Thorium Based Reactors
30 kWth KAMINI- Operating
300 MWe AHWR Under Development
MSBR
POWER POTENTIAL FOR STAGE-III IS VERY LARGE
Proven technology
Globally Advanced Technology
Globally Unique
IWAAP th Nov 2017 Mumbai

5. Nuclear power plants in India
Nuclear power is the only mature non-carbon energy generation option.
Nuclear energy entails re-use or recycle of nuclear fuels thereby increasing its energy potential.
India’s installed capacity
IWAAP th Nov 2017 Mumbai

6. Three stage Indian Nuclear Power Programme
NFC
PHWR
IRE
FUEL REPROCESSING
PLANTS
NON-REACTOR
BREEDING
ADVANCED FUEL
FABRICATION
FAST
BREEDER
REACTORS
ADVANCED HEAVY WATER
THORIUM - U233 FUELLED
WIP
SSSF
REPOSITORY
U FUEL Th
Zr-ALLOYS Zr
Th + U233
U+Pu
Th+U233
WASTE Pu U
U233
FUEL
PLAIN
Th+U233FUEL
U+PuFUEL
DEP. U
BLANKET
ZIRCALOY PRODUCT
(U+Pu ) FUEL
(U+ Pu ) FUE L
(U+Pu) FUEL (Pu RECYCLE)
Th + U233
UCIL
1st STAGE
2nd STAGE
3rd STAGE
Material flow as plant starts working
Material flow at subsequent stages
Future possibility
Th+ U233
IWAAP th Nov 2017 Mumbai

7. Research reactors in India
IWAAP th Nov 2017 Mumbai

8. Nuclear reactors in India : Research Reactors
APSARA – (De-commissioned) (1956)
U-Al Alloy plate type fuel ; Light water
CIRUS (Decommisioned recently) (1960)
U metal ; Light water coolant ; Heavy water moderator ;
40 MW ;Neutron flux 6.5 x n/cm2/s
DHRUVA MWth research reactor (1985)
U metal : Heavy water coolant; Heavy water Moderator
100 MW 1.8 x 1014 n/cm2/s
KAMINI- 30 kW 233U-Th based reactor for neutron radiography
Only reactor in the world operating with thorium fuel
PURNIMA I (PuO2)&II (U-233 nitrate solution)
(Experimental reactors) (1972,1984)
PURNIMA III (233U-Al ; Light water ;Mock-up for KAMINI) (1990)
ZERLINA ( De-commissioned) (1961)
Nat. U metal ; Heavy water moderator and coolant : Reactor lattice studies)
Critical Facility for AHWR (100 W – for Reactor Physics validation)
Future reactors
Upgraded APSARA (2 MWth) ; High Flux Research Reactor
KAMINI research reactor: 233U-Al Fuel
Core layout of AHWR Critical Facility
IWAAP th Nov 2017 Mumbai

9. Glimpses of research reactors
Uses
Basic research
Radio isotope production
Material testing
Fuel irradiation
Activation analysis
Neutron scattering experiments
A critical facility for new reactor design
KAMINI research reactor: 233U-Al Fuel
Latest research reactor in the world : Jules Horowitz Reactor, Cadarache Southern France
IWAAP th Nov 2017 Mumbai

10. Dhruva Reactor : General Features
Fuel : Nat. U metal
Coolant : Heavy water
Moderator : Heavy Water
Rated power : 100 MWth
Design neutron flux : 1.8 x 1014n/cm2/s
Uses
Basic research
Radio isotope production
Fuel irradiation
Activation analysis
Neutron scattering experiments
Typical power distribution in Dhruva core
IWAAP th Nov 2017 Mumbai

11. Fast Breeder Test Reactor (FBTR)
DESIGN PARAMETERS
• Rated for 40MWt /13.2MWe with 65 MOX fuel SA
• Currently rated for 22.5MWt/5MWe with smaller core of PuC+UC fuel SA
• LHR of fuel 400W/cm
• Neutron flux ×10 15 n/cm 2/sec
• Py. sodium flow 1100 m 3/h
• Reactor inlet/outlet temp. 380/515C
• Feed water flow 70 t/h & temp 180 C
• Steam conditions 480 C & 125Kg/cm
Milestones achieved
Reactor physics and safety related experiments
Experience with fuel
Irradiation of MOX fuel upto 112 GWd/te
Experience with sodium reactor technology
Closed fuel cycle with Pu
IWAAP th Nov 2017 Mumbai

12. KAMINI - the only reactor operating with 233U as fuel in the whole world now
KAMINI (KAlpakkam MINI) is a 30 kWth, 233U (20 wt%) -Al alloy fuelled, demineralised light water moderated and cooled, special purpose research reactor. Beryllium oxide (BeO) is used as reflector and cadmium is used as absorber material in the safety control plates. The reactor functions as a neutron source with a flux of 1012 n/cm2/s at the core center. Core cooling is by natural circulation of the coolant. It is used for:
Neutron radiography of both radioactive and non-radioactive objects (e.g. FBTR fuel pins)
Neutron activation analysis.
Carrying out radiation physics research,
Irradiation of large number of samples, and
Calibration and testing of neutron detectors.
Neutron radiography of MOX fuel pin
Chandrayaan (Indian lunar probe) mission critical devices were successfully inspected at KAMINI
Neutron radiography of irradiated FBTR control rod
Neutron radiography of space components
IWAAP th Nov 2017 Mumbai 12

13. Critical Facility for AHWR physics design validation
Critical Facility went critical on 7th April, 2008.
AHWR Critical Facility has been designed for conducting lattice physics experiments to validate AHWR physics calculations.
Fuel: 19 pin Nat. U metal in reference core
Moderator : D2 O
Flexibility to vary the lattice pitch for physics study
Experiments performed
Measurement of critical height for various cores
Calibration of reactivity devices.
Level coefficient measurement.
Neutron Spectrum measurement on central cluster.
Cadmium ratio measurement at infinite dilution.
Fine structure flux measurement inside the central fuel location with Nat. Uranium and thorium clusters.
Measurement of Moderator and Coolant Void Coefficient of reactivity.
Integral measurement s with Mixed Pin (Nat. U-ThO2) and(Th,Pu)MOX experimental cluster
The validation exercise has raised the confidence level in calculation methodology and simulations
IWAAP th Nov 2017 Mumbai

14. Experimental ADS Facility :BRAHMMA
BRAHMMA :Beryllium oxide Reflected and HDP Moderated Multiplying Assembly
Sub-critical Assembly (Keff~0.9)
Fuel:Nat U (Rad:1.72 cm; Length:130 cm)
160 No fuel rod Pitch~4.8 cm Clad:Al
Moderator:HDP Reflector:BeO
Central 3X3 region is for Neutron source
Lead plug at backside to stop the streaming
Neutron source: DD/DT Accelerator
Experiments (N&XFD and RPDD)
Measurement of reactivity
Neutron noise methods
Area Ratio methods
Source jerk method
Axial flux distribution
Side view
Lead Plug
Plan view
Ref: BeO
IWAAP th Nov 2017 Mumbai

15. JHR CEA
IWAAP th Nov 2017 Mumbai

16. A brief overview of power reactors in India
IWAAP th Nov 2017 Mumbai

17. Nuclear reactors in India : Power Reactors
BWR (Boiling Water Reactor)
TAPS 1 & 2 (BWR – General Electric)
Enriched U ( 235U) ~ 2.1% Light water cooled and moderated
160 MW(e) MWd/T : Batch fuelling
PHWR (Pressurised Heavy Water Reactor)
Nat. UO2 ; Heavy water moderator, Heavy water coolant
RAPS 1 & 2 (CANDU) 3,4,5, & 6
MAPS 1&2 (220 MW(e))
KGS 1,2,3, & 4
NAPS 1&2
KAPS 1&2
TAPS 3 & 4 ( 540 MW(e) )
PWR (Pressurised Water Reactor)
VVER Kudankulam (PWR) – 2 x 1000 MW(e
Projects in the pipeline
PFBR ( Fast Reactor) [500 MW(e)]
VVER KK 3&4(PWR) – [2 x 1000 MW(e)],
RAPS 7 & 8 [2 x 700 MW(e)]
KAPS 3 &4 [2 x 700 MW(e)]
GHAVP 1&2 [2x 700 MW(e)]
2 BWRs, 18 PHWRs, 2 VVER
generating about
6780 MW(e)
~ 3% of total electricity generated in India
IWAAP th Nov 2017 Mumbai

18. Pressurised Heavy Water Reactor : Salient features
19 Pin Cluster for 220 MWe PHWR
Pressure tube type of reactor : Coolant is pressurised
Low temperature moderator
Fuel is in the form of short length bundles
Coolant flows in opposite directions in adjacent channels
On power fuelling
Discharge burnup 6700 MWd/T
Cobalt adjusters (control) / SS adjusters (540 MW(e))
Cadmium shut-off rods
220 MW(e) , 540 MW (e)---- scaling to 700 MW (e)
37 Pin Cluster for 540 MWe PHWR
IWAAP th Nov 2017 Mumbai

19. Pressurised Heavy Water Reactor (PHWR)
Schematic of PHWR
PHWRs constitute about 11% of the nuclear power reactors in the world
Salient features of the reactor
Power level 756 MWth/220 MWe
Horizontal pressure tube type design
Moderator - Heavy Water
Primary coolant - Heavy Water
On-power refuelling
Fuel - Natural UO2 (Reference case)
Circular fuel geometry
Lattice pitch mm square pitch
Number of coolant channels - 306
Fuel burn up- 6.7 GWd/te
IWAAP th Nov 2017 Mumbai 19

20. Boiling Water Reactor (BWR) :: TAPS 1 &2
Differential enrichment inside an assembly
Fuel management by batch fuelling
Steam produced directly in the core
IWAAP th Nov 2017 Mumbai

21. A typical Equilibrium BWR Core with batch mode of refueling
BWR core showing batch loading fuel
IWAAP th Nov 2017 Mumbai

22. Prototype Fast breeder Reactor (PFBR)
Salient features of the PFBR
Power level 500 MW(e) /1250 MWth
UO2; PuO2 with Dep UO2 radial and axial blankets
Burnup ~100 GWD/Te
Liquid sodium cooled : pool type
2 secondary loops
Cycle length EFPD
Partial core is repalced
IWAAP th Nov 2017 Mumbai

23. Future power reactors in India
IWAAP th Nov 2017 Mumbai

24. AHWR : Thorium fuelled reactor design
The Advanced Heavy Water Reactor (AHWR) is a unique reactor designed in India for the large scale commercial utilisation of thorium and integrated technological demonstration of the thorium cycle
Design objectives / Challenges
Maximise the power from thorium
Maximise the in-situ burning of 233U
Negative power coefficient in linear range of power
Heat removal through natural circulation
Uniform coolant flow ; flat radial power distribution , short active core height
Low power density
Bottom peaked axial power/flux distribution
Fuel cycle aspects
Self-sustenance in 233U
Plutonium as make-up fuel ; minimise the Pu inventory and consumption
Maximise the burnup
AHWR fuel cluster
Important Design Parameters of AHWR
Reactor Power
300 MWe (920MWth)
Fuel
54 pin cluster
(Th,233U)MOX+(Th,Pu) MOX
Enrichment
Inner / Middle / Outer
233U=3%,3.75%, Pu=3.25%
Coolant
Boiling Light Water
Moderator
Heavy Water
Total No. of Channels
513
No. of Fuel Channels
452
Lattice Pitch
225 mm
Primary Shut down System
37 shut off rods (B4C absorber)
Secondary Shut down System
Liquid poison injection
No. of Control Rods 24
Passive Poison Injection
Poison injection through a passive valve
These are not essentially evolutionary in nature; required totally a new thinking.
IWAAP th Nov 2017 Mumbai

25. A typical AHWR equilibrium core
Typical thermal flux profile across the core mid plane
IWAAP th Nov 2017 Mumbai

26. Physics design of IPWR Design objectives Design features
Target discharge burnup ~50,000 MWd/t
Reactor power is 900 MW(e) / 2700 MW(th)
Enriched Uranium as fuel in a once through multi-batch fuel cycle mode
Minimising the soluble boron content
Achieve a better local peaking factors by way of using Gadolinium as IFBA (Integral Fuel Burnable Absorber) in the fuel
All reactivity feedbacks should be negative
Neutron monitorability of the core at all stages
Design features
IPWR core has been designed to provide 2700
MWt (900 MWe) over an equilibrium cycle length of
410 days.
An average enrichment of 4.22% has been used to
obtain a discharge burnup ~46 GWD/T
The reactivity management is by soluble boron and rod cluster control
All the reactivity coefficients are negative during any operating regime within the entire range of parameter variation
Core layout of IPWR
IWAAP th Nov 2017 Mumbai

27. Basic Characteristics of CHTR
Fuel Tubes
Graphite Reflector
PPRS
Downcomers
BeO Moderator
Reactor Power
100 kWth
Core Life
15 years
Fuel
U-233 Mixed with Th in carbide form
Fuel Mass
U Th
Coolant
Lead-Bismuth Eutectic
No. of Fuel Tubes 19
ID/OD of Fuel Tubes
35/75 mm
Hexagonal Pitch
13.5 cm
Moderator
BeO (Density 2.9 g/cc)
Reflector
BeO and Graphite
Passive Power Regulation & Shutdown System (PPRS)
B4C absorbers in 18 BeO blocks
Secondary SDS
W rods in inner 7 coolant Channels
Layout of the CHTR core
Dense Pyrocarbon (PyC) Layer
SiC Layer
Kernel
Buffer
CHTR TRISO Coated Fuel Particle
(Typical dimension :900 m )
Typical radial power distribution : Peaking factors
IWAAP th Nov 2017 Mumbai

28. Some simulation and experimental results
IWAAP th Nov 2017 Mumbai

29. Nuclear data measurement to physical constants for potential applications
The n_TOF facility at CERN
IWAAP th Nov 2017 Mumbai

30. Spectral indices : How thermal is a thermal reactor ?
PHWR
AHWR
PWR
BWR
PFBR
Average energy
0.08 eV
0.45 eV
5.5 eV
2.44 eV
400 keV
Epithermal –to-Thermal ratio
0.52
1.82
7.5
5.2 -
Fissions below eV (%) 96 80 73
Average thermal flux
n/cm2 /s
2.1 x 1014
7.3 x 1013
6.1 x1013
Neutron flux in thermal reactors
Physics design aims at optimsing the fuel performance w.r.t net reaction rates
Maximise the fissile production and fertile captures for breeding
In thermal reactors
Maximise thermal fission reaction rates
IWAAP th Nov 2017 Mumbai

31. Core power distribution :: PHWR
IWAAP th Nov 2017 Mumbai

32. Neutron spectrum and reaction cross section in AHWR fuel
Outer Containment
Inner Containment
Tail Pipe Tower
Calandria
Raft
Gravity Driven Water Pool
Neutron spectrum at different locations
Neutron flux contours in X-Y plane
Neutron and gamma flux profile from core centre
IWAAP th Nov 2017 Mumbai

33. Fission reaction rates with irradiation in different thermal spectra
IPWR
PHWR
AHWR-Pu-U
AHWR-LEU
IWAAP th Nov 2017 Mumbai

34. A few results from AHWR-CF
Fine structure flux by activation foils in removable fuel pins in experimental cluster
Absolute reaction rate #/cm2
Absolute reaction rate #/cm2
Measured axial flux distribution (Cu wire)
Axial distance in mm
Axial Neutron Flux Distribution Inside and Around E5 Central Cluster Using Cadmium Covered Gold Foils
Radial distance in mm
Radial Neutron Flux Distribution
Gamma scanning of Fuel pin irradiated in AHWR-CF
Neutron Spectrum Measurement
Measured reaction rates used to calibrate flux mapping system (FCs)
IWAAP th Nov 2017 Mumbai

35. Thank you…..
IWAAP th Nov 2017 Mumbai

36. Thank you Gravity Driven Water Pool Inner Containment Tail Pipe Tower
Outer Containment
Inner Containment
Tail Pipe Tower
Calandria
Raft
Gravity Driven Water Pool
Thank you
Fresh fuel
Discharged fuel channel
Outer zone
Inner zone
Middle zone
Refueling with double reshuffling