An overview of nuclear reactor facilities in India Umasankari Kannan Reactor Physics Design Division Bhabha atomic Research Centre uma_k@barc.gov.in IWAAP 2017 30th Nov 2017 Mumbai

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 2017 30th Nov 2017 Mumbai

The Indian nuclear power programme IWAAP 2017 30th Nov 2017 Mumbai

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 2017 30th Nov 2017 Mumbai

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 2017 30th Nov 2017 Mumbai

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 2017 30th Nov 2017 Mumbai

Research reactors in India IWAAP 2017 30th Nov 2017 Mumbai

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 1013 n/cm2/s DHRUVA - 100 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 2017 30th Nov 2017 Mumbai

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 2017 30th Nov 2017 Mumbai

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 2017 30th Nov 2017 Mumbai

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 - 3.15 ×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 2017 30th Nov 2017 Mumbai

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 2017 30th Nov 2017 Mumbai 12

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 2017 30th Nov 2017 Mumbai

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 2017 30th Nov 2017 Mumbai

JHR CEA IWAAP 2017 30th Nov 2017 Mumbai

A brief overview of power reactors in India IWAAP 2017 30th Nov 2017 Mumbai

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) 20000 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 2017 30th Nov 2017 Mumbai

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 2017 30th Nov 2017 Mumbai

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- 228.6 mm square pitch Number of coolant channels - 306 Fuel burn up- 6.7 GWd/te IWAAP 2017 30th Nov 2017 Mumbai 19

Boiling Water Reactor (BWR) :: TAPS 1 &2 Differential enrichment inside an assembly Fuel management by batch fuelling Steam produced directly in the core IWAAP 2017 30th Nov 2017 Mumbai

A typical Equilibrium BWR Core with batch mode of refueling BWR core showing batch loading fuel IWAAP 2017 30th Nov 2017 Mumbai

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 - 185 EFPD Partial core is repalced IWAAP 2017 30th Nov 2017 Mumbai

Future power reactors in India IWAAP 2017 30th Nov 2017 Mumbai

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 2017 30th Nov 2017 Mumbai

A typical AHWR equilibrium core Typical thermal flux profile across the core mid plane IWAAP 2017 30th Nov 2017 Mumbai

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 2017 30th Nov 2017 Mumbai

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-233 + 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 2017 30th Nov 2017 Mumbai

Some simulation and experimental results IWAAP 2017 30th Nov 2017 Mumbai

Nuclear data measurement to physical constants for potential applications The n_TOF facility at CERN IWAAP 2017 30th Nov 2017 Mumbai

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 0.625 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 2017 30th Nov 2017 Mumbai

Core power distribution :: PHWR IWAAP 2017 30th Nov 2017 Mumbai

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 2017 30th Nov 2017 Mumbai

Fission reaction rates with irradiation in different thermal spectra IPWR PHWR AHWR-Pu-U AHWR-LEU IWAAP 2017 30th Nov 2017 Mumbai

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 2017 30th Nov 2017 Mumbai

Thank you….. IWAAP 2017 30th Nov 2017 Mumbai

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