Bhabha Atomic Research Centre
भाभा परमाणु अनुसंधान केंद्र | |
Abbreviation | BARC |
---|---|
Formation | 3 January 1954[1] |
Founder | Homi J. Bhabha |
Headquarters | Trombay, Mumbai |
Location |
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Locations | |
Coordinates | 19°01′01″N 72°55′30″E / 19.017°N 72.925°E |
Fields |
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Director | Vivek Bhasin |
Parent organisation | Department of Atomic Energy |
Budget | ₹4,086 crore (US$510 million) (2020–21) |
Website | barc |
Formerly called | Atomic Energy Establishment, bombay |
[2] |
The Bhabha Atomic Research Centre (BARC) is India's premier
BARC is a multi-disciplinary research centre with extensive infrastructure for advanced research and development covering the entire spectrum of
BARC's core mandate is to sustain peaceful applications of
Its primary facilities are located in Trombay, with new facilities also located in Challakere in Chitradurga district of Karnataka. A new Special Mineral Enrichment Facility which focuses on enrichment of uranium fuel is under construction[when?] in Atchutapuram near Visakhapatnam in Andhra Pradesh, for supporting India's nuclear submarine program and produce high specific activity radioisotopes for extensive research.
History
When Homi Jehangir Bhabha was working at the
When Bhabha realised that technology development for the atomic energy programme could no longer be carried out within
Bhabha established the BARC Training School to cater to the manpower needs of the expanding atomic energy research and development program. Bhabha emphasized self-reliance in all fields of nuclear science and engineering.
The Government of India created the Atomic Energy Establishment,
The first reactors at BARC and its affiliated power generation centres were imported from the west. India's first power reactors, installed at the Tarapur Atomic Power Station were from the United States.
The primary importance of BARC is as a research centre. The BARC and the Indian government has consistently maintained that the reactors are used for this purpose only: Apsara (1956; named by the then Prime Minister of India,
Along with DRDO and other agencies and laboratories BARC also played an essential and important role in nuclear weapons technology and research. The plutonium used in India's 1974 Smiling Buddha nuclear test came from CIRUS. In 1974 the head of this entire nuclear bomb project was the director of the BARC, Raja Ramanna. The neutron initiator was of the polonium–beryllium type and code-named Flower was developed by BARC. The entire nuclear bomb was engineered and finally assembled by Indian engineers at Trombay before transportation to the test site. The 1974 test (and the 1998 tests that followed) gave Indian scientists the technological know-how and confidence not only to develop nuclear fuel for future reactors to be used in power generation and research but also the capacity to refine the same fuel into weapons-grade fuel to be used in the development of nuclear weapons.
BARC was also involved in the
On 3 June 1998 BARC was hacked by
BARC also designed a class of Indian Pressurized Heavy Water Reactor IPHWR (Indian Pressurized Heavy Water Reactor), the baseline 220 MWe design was developed from the Canadian CANDU reactor. The design was later expanded into 540 MW and 700 MW designs.
The IPHWR-220 (Indian Pressurized Heavy Water Reactor-220) was the first in class series of Indian pressurized heavy-water reactor designed by the Bhabha Atomic Research Centre. It is a Generation II reactor developed from earlier CANDU based RAPS-1 and RAPS-2 reactors built at Rawatbhata, Rajasthan. Currently there are 14 units operational at various locations in India. Upon completion of the design of IPHWR-220, a larger 540 MWe design was started around 1984 under the aegis of BARC in partnership with NPCIL.[6] Two reactors of this design were built in Tarapur, Maharashtra starting in the year 2000 and the first was commissioned on 12 September 2005. The IPHWR-540 design was later upgraded to a 700 MWe with the main objective to improve fuel efficiency and develop a standardized design to be installed at many locations across India as a fleet-mode effort. The design was also upgraded to incorporate Generation III+ features. Almost 100% of the parts of these indigenously designed reactors are manufactured by Indian industry.
BARC designed and built India's first
BARC also developed stabilization systems for Seekers, Antenna Units for India's multirole fighter
In 2012 it was reported that new facilities and campuses of BARC were planned in Atchutapuram, near Visakhapatnam in Andhra Pradesh, and in Challakere in Chitradurga district in Karnataka. BARC would be setting 30 MW special research reactor using an enriched uranium fuel at Visakhapatnam to meet the demand for high specific activity radio isotopes and carry out extensive research and development in nuclear sector. The site would also support the nuclear submarine program.[11][12]
Description
BARC is a multi-disciplinary research centre with extensive infrastructure for advanced research and development covering the entire spectrum of nuclear science, chemical engineering, material sciences and metallurgy, electronic instrumentation, biology and medicine, supercomputing, high-energy physics and plasma physics and associated research for Indian nuclear programme and related areas.
BARC is a premier nuclear and multi-disciplinary research organisation though founded primarily to serve India's nuclear program and its peaceful applications of nuclear energy does an extensive and advanced research and development covering the entire spectrum of nuclear science,
Organisation and governance
BARC is an agency of the Department of Atomic Energy.[13] It is divided into a number of Groups, each under a director, and many more Divisions.[14]
Nuclear Recycle Board
BARC's Nuclear Recycle Board (NRB) was formed in 2009.[15] It is located in three cities – Mumbai, Tarapur, and Kalpakkam.[16]
Areas of research
BARC conducts extensive and advanced research and development covering the entire spectrum of nuclear science, chemical engineering, material sciences and metallurgy, electronics instrumentation, biology and medicine, advance computing, high-energy plasma physics and associated research for Indian nuclear program and related areas. The few are:
Thorium fuel cycle
India has a unique position in the world, in terms of availability of nuclear fuel resource. It has a limited resource of
Post-irradiation examinations have been carried out on the irradiated PHWR thoria fuel bundles and (Th-Pu) MOX fuel pins. Thermo-physical and thermodynamic properties have been evaluated for the thoria based fuels. Thoria fuel rods irradiated in CIRUS have been reprocessed at Uranium Thorium Separation Facility (UTSF) BARC. The recovered 233U has been fabricated as fuel for KAMINI reactor. Thoria blanket assemblies irradiated in
Advanced reactors
Reprocessing and nuclear waste management
After certain energy utilization, known as burn-up (a legacy of thermal power) is reached, nuclear fuel in a reactor is replaced by fresh fuel so that
Implementation of
High Level Liquid Waste (HLLW) generated during reprocessing of spent fuel contains most of the
Vitrification Cell (IHMM), WIP, Trombay Joule Heated Ceramic Melter, Tarapur Inside view of Cold Crucible Induction Melter R&D in the field of partitioning of Minor
Advanced Fuel Fabrication Facility
The Advanced Fuel Fabrication Facility (AFFF), a MOX fuel manufacturing facility,[19][20] is part of the Nuclear Recycle Board (NRB),[21] and located at the Tarapur, Maharashtra. Advanced Fuel Fabrication Facility has fabricated MOX fuels on experimental basis for BWR, PHWR, FBTR and research reactors. It makes plutonium-based MOX fuel for the stage 2 of Indian Nuclear Program. The unit successfully has produced 1,00,000 fuel pins for the Kalpakam based Bhavini's PFBR.
MOX fuel fabrication at AFFF follows Powder Oxide Pelletisation (POP) Method. PFBR however, has faced quiet significant delays over the years.[22][23]
Basic and applied physics
The interdisciplinary research includes investigation of matter under different physicochemical environments, including temperature, magnetic field and pressure. Reactors,
The Low Energy High Intensity Proton Accelerator (LEHIPA) project is under installation at common facility building in BARC premises. The 20 MeV, 30 mA, CW proton linac will consist of a 50 keV ion source, a 3 MeV, 4 m long, radio-frequency quadrupole (RFQ) and a 3-20 MeV, 12 m long, drift-tube linac (DTL) and a beam dump.
Ongoing basic and applied research encompasses a broad spectrum covering
Some of the important ongoing developmental activities are: Indian Scintillat or Matrix for Reactor Anti-Neutrinos (ISMRAN), neutron guides,
High-performance computing
BARC designed and developed a series of
The latest in the series is Anupam-Aganya[25] BARC has started development of supercomputers under the ANUPAM project in 1991 and till date, has developed more than 20 different computer systems. All ANUPAM systems have employed
The series started with a small four-processor system in 1991 with a sustained performance of 34 MFlops. Keeping in mind the ever increasing demands from the users, new systems have been built regularly with increasing computational power. The latest in the series of supercomputers is Anupam-Aganya with processing power of 270 TFLOPS and PARALLEL PROCESSING SUPERCOMPUTER ANUPAM-ATULYA:Provides sustained LINPACK performance of 1.35 PetaFlops for solving complex scientific problems.[10]
Electronics instrumentation and computers
BARC's research and development programing electrical, electronics, instrumentation and computers is in the fields of Nuclear Science and Technology, and this has resulted in the development of various indigenous technologies.
In the fields of nuclear energy, many Control and Instrumentation systems including In Service Inspection Systems were designed, developed and deployed for Nuclear Reactors ranging from
Core competencies cover a wide spectrum and include Process Sensors,
Generic electronic products like Qualified
Material Sciences and Engineering
Research aimed at advanced materials technologies using Thermodynamics, Mechanics, Simulation and Modelling, characterisation and performance evaluation is done. Studies aimed at understanding radiation damage in materials are undertaken using advanced characterization techniques to help in alloy development and material degradation assessment activities. Generation of thermo-physical and defect property database of nuclear materials e.g., Thoria-based Mixed oxide and metallic fuels; studies on Fe-Zr alloys and natural and synthetic minerals as hosts for metallic waste immobilization through modelling and simulations is being pursued.
Development of novel solvents to extract selected elements from the nuclear waste for medical applications and specific metallic values from
Chemical Engineering and Sciences
The key features underlying the development effort are self-reliance, achieving products with very high purity specifications, working with separation processes characterized by low separation factors, aiming high recoveries, optimal utilization of scarce resources, environmental benignity, high energy efficiency and stable continuous operation. Non-power application of nuclear energy has been demonstrated in the area of water desalination using the technologies such as Multi Stage Flash Distillation and Multi Effect Distillation with Thermo Vapor Compression (MED-TVC). Membrane technologies have been deployed not only for nuclear waste treatment but for society at large in line with the Jal Jeevan Mission of Government of India to provide safe drinking water at the household level.
Development and demonstration of fluidized bed technology for applications in nuclear fuel cycle; synthesis and evaluation of novel extractants; synthesis of TBM materials (synthesis of
A pre-cooled modified Claude cycle based 50 L/hr capacity helium liquefier (LHP50) has been developed and commissioned by BARC at Trombay. Major component technologies involved in LHP50 include ultra-high speed gas bearing supported miniature turboexpanders and compact plate fin
Environment, Radiology and Radiochemical Science
BARC also monitors Environmental impact and dose / risk assessment for radiological and chemical contaminants, Environmental surveillance and radiation protection for the entire nuclear fuel cycle facilities, Meteorological and hydro-geological investigations for DAE sites. Modelling of contaminant transport and dispersion in the atmosphere and hydrosphere, Radiological impact assessment of waste management and disposal practices, Development of Environmental Radiation Monitoring systems and Establishment of country wide radiation monitoring network, establishment of benchmarks for assessing the radiological impact of the nuclear power activities on the marine environment. The highlights of these programs are Positron and positronium chemistry, Actinide chemistry and spectroscopy, Isotope hydrology for water resource management, Radiotracer for Industrial Applications, Separation and purification of new, radionuclides for medical applications, Advance fuel development by sol gel method, Chemical quality control of nuclear fuels, Complexation and speciation of actinides, Separation method development for back end fuel cycle processes.
The other major research projects are thermo-physical property evaluation of molten salt breeder reactor (MSBR) systems, development of core-catcher materials, hydrogen mitigation, catalysts for hydrogen production, hydrogen storage materials, nanotherapeutics and bio-sensors, decontamination of reactor components, biofouling control and thermal ecology studies, supramolecular chemistry, environmental and interfacial chemistry, ultrafast reaction dynamics, single molecule spectroscopy, synthesis and applications of nanomaterials, cold plasma applications, luminescent materials for bio-imaging, materials for light emitting devices and security applications etc.
Health, Food and agriculture
Development of new elite crop varieties including oil seeds and pulses. Using radiation-induced mutagenesis, hybridization, and tissue culture techniques 49 crop varieties have been developed, released and Gazette-notified for commercial cultivation. Development of molecular markers, transgenics, biosensors, fertilizer formulations with improved nutrient use efficiency. Understanding DNA damage repair, replication, redox biology and autophagy process and development of radio-sensitizers, chemo-sensitizers for cancer therapy. Design and synthesis of organo-fluorophores and organic electronic molecules, relevant to nuclear sciences and societal benefits (advanced technology and health). Design and synthesis of organo-fluorophores and organic electronic molecules, relevant to nuclear sciences and societal benefits (advanced technology and health).[28]
Synthesis and development of nuclear medicine ligands for diagnosis and therapy of cancer and other diseases. Asymmetric total synthesis and organocatalytic methods (green chemistry approach) for the synthesis of biologically active compounds. R&D activities in the frontier areas of radiation biology for understanding the effect of low- and high LET radiations, chronic and acute radiation exposure, high background radiation, and radionuclide exposure on mammalian cells, cancer cells, experimental rodents and human health.[28]
Preclinical and translational research is aimed at development of new drugs and therapeutics for prevention and mitigation of radiation injury, de-corporation of heavy metals and treatment of inflammatory disorders and cancers. Studying macromolecular structures and protein-ligand interactions using biophysical techniques like X-ray crystallography, neutron-scattering, circular dichroism and synchrotron radiation, with an aim for ab-initio design of therapeutic molecules. Understanding the cellular and molecular basis of stress response in bacteria, plants and animals. Understanding the extraordinary resistance to DNA damage and oxidative stress tolerance in bacteria, and epigenetic regulation of alternate splicing in plants and mammalian cells.[28]
Development of CRISPR-Cas mediated genome editing technologies in both basic and applied research and is engaged in the development of gene technologies and products for bio-medical applications. Studies on uranium sequestration by Nostoc and bacteria isolated from uranium mines. Research and development of novel radiopharmaceuticals for diagnostic and therapeutic purposes.[28]
Synthesis of substrates from suitable precursors for use in radio-labeling with diagnostic (99mTc) and therapeutic (177Lu, 153Sm, 166Ho, 186/188Re, 109Pd, 90Y, 175Yb, 170Tm) radioisotopes in the preparation of agents intended for use as radiopharmaceuticals. Custom preparation of special sources to suit the requirements of the Defense Research Organization of India (DRDO) and National Research Laboratories such as National Physics Research Laboratory, ISRO etc.[28]
India's three-stage nuclear power programme
India's three-stage nuclear power programme was formulated by Homi Bhabha in the 1950s to secure the country's long term energy independence, through the use of uranium and thorium reserves found in the monazite sands of coastal regions of South India. The ultimate focus of the programme is on enabling the thorium reserves of India to be utilised in meeting the country's energy requirements. Thorium is particularly attractive for India, as it has only around 1–2% of the global uranium reserves, but one of the largest shares of global thorium reserves at about 25% of the world's known thorium reserves.[29]
Stage I – Pressurised Heavy Water Reactor
In the first stage of the programme, natural uranium fueled pressurised heavy water reactors (PHWR) produce electricity while generating plutonium-239 as by-product. PHWRs was a natural choice for implementing the first stage because it had the most efficient reactor design in terms of uranium utilisation, and the existing Indian infrastructure in the 1960s allowed for quick adoption of the PHWR technology. Natural uranium contains only 0.7% of the fissile isotope uranium-235. Most of the remaining 99.3% is uranium-238 which is not fissile but can be converted in a reactor to the fissile isotope plutonium-239. Heavy water (deuterium oxide, D2O) is used as moderator and coolant.[30]
Stage II – Fast Breeder Reactor
In the second stage, fast breeder reactors (FBRs) would use a mixed oxide (MOX) fuel made from plutonium-239, recovered by reprocessing spent fuel from the first stage, and natural uranium. In FBRs, plutonium-239 undergoes fission to produce energy, while the uranium-238 present in the mixed oxide fuel transmutes to additional plutonium-239. Thus, the Stage II FBRs are designed to "breed" more fuel than they consume. Once the inventory of plutonium-239 is built up thorium can be introduced as a blanket material in the reactor and transmuted to uranium-233 for use in the third stage The surplus plutonium bred in each fast reactor can be used to set up more such reactors, and might thus grow the Indian civil nuclear power capacity till the point where the third stage reactors using thorium as fuel can be brought online. The design of the country's first fast breeder, called Prototype Fast Breeder Reactor (PFBR), was done by Indira Gandhi Centre for Atomic Research (IGCAR).[31]
Doubling time
Doubling time refers to the time required to extract as output, double the amount of fissile fuel, which was fed as input into the breeder reactors. This metric is critical for understanding the time durations that are unavoidable while transitioning from the second stage to the third stage of Bhabha's plan, because building up a sufficiently large fissile stock is essential to the large deployment of the third stage.[32]
Stage III – Thorium Based Reactors
A Stage III reactor or an Advanced nuclear power system involves a self-sustaining series of thorium-232–uranium-233 fuelled reactors. This would be a thermal breeder reactor, which in principle can be refueled – after its initial fuel charge – using only naturally occurring thorium. According to the three-stage programme, Indian nuclear energy could grow to about 10 GW through PHWRs fueled by domestic uranium, and the growth above that would have to come from FBRs till about 50GW.[b] The third stage is to be deployed only after this capacity has been achieved.[33][34]
Parallel approaches
As there is a long delay before direct thorium utilisation in the three-stage programme, the country is looking at reactor designs that allow more direct use of thorium in parallel with the sequential three-stage programme. Three options under consideration are the Indian Accelerator Driven Systems (IADS),
India's Department of Atomic Energy and US's Fermilab are designing unique first-of-its-kind accelerator driven systems. No country has yet built an Accelerator Driven System for power generation. Anil Kakodkar, former chairman of the Atomic Energy Commission called this a mega science project and a "necessity" for humankind.[35][36]
Reactor design
BARC has developed a wide array of nuclear reactor designs for nuclear research, production of radioisotopes, naval propulsion and electricity generation
Research reactors and production of radioisotopes
Reactor | Purpose and History[37] |
---|---|
APSARA | Apsara was India's first nuclear reactor built at BARC in 1956 to conduct basic research in nuclear physics. It is 1 MWTh light water cooled and moderated swimming pool type thermal reactor that went critical on 4 August 1956 and is suitable for production of isotopes, basic nuclear research, shielding experiments, neutron activation analysis, neutron radiography and testing of neutron detectors. It was shutdown permanently in 2010 and replaced with Apsara-U |
APSARA-U | Apsara-U or Apsara-Upgraded is a replacement for APSARA. It is 2 MWTh light water cooled and moderated swimming pool type thermal reactor fuelled with uranium silicide. It went critical on September 10, 2018, and is suitable for production of isotopes, basic nuclear research, shielding experiments, neutron activation analysis and testing of neutron detectors. |
ZERLINA | ZERLINA was a Heavy water cooled and moderated vertical tank type thermal reactor built to conduct reactor lattice studies that first went critical on 14 January 1961. It was decommissioned in 1983. |
Dhruva | Dhruva is a 100 MWth heavy water moderated and cooled vertical tank type thermal reactor primarily used for production of radioisotopes and weapons grade plutonium-239 for nuclear weapons and was successor to the Canadian built CIRUS reactor at BARC. It first went critical on August 8, 1985, and was later upgraded in the late 2010s.[38] |
Purnima-I | Purnima-I is a Plutonium oxide fuelled 1 MWTh pulsed-fast reactor that was built starting in 1970 and went critical on 18 May 1972 to primarily support the validation of design parameters for development of Plutonium-239 powered nuclear weapons.[38] On the twentieth anniversary of the 1974 Pokhran nuclear test, Purnima's designer, P. K. Iyengar, reflected on the reactor's critical role: " Purnima was a novel device, built with about 20 kg of plutonium, a variable geometry of reflectors, and a unique control system. This gave considerable experience and helped to benchmark calculations regarding the behaviour of a chain-reacting system made out of plutonium. The kinetic behaviour of the system just above critical could be well studied. Very clever physicists could then calculate the time behaviour of the core of a bomb on isotropic compression. What the critical parameters would be, how to achieve optimum explosive power, and its dependence on the first self sustaining neutron trigger, were all investigated".[38] It was decommissioned in 1973. |
Purnima-II | Purnima-II is Uranium-233 fuelled 100 mW vertical tank type thermal reactor built to support Uranium-233 fuel studies and was decommissioned in 1986. |
Purnima-III | Purnima-III Uranium-233 fuelled 1 WTh vertical tank type thermal reactor built to conduct mockup studies for the KAMINI reactor built at IGCAR, Kalpakkam. It was decommissioned in 1996. |
FBTR | The Fast Breeder Test Reactor (FBTR) is a breeder reactor located at Kalpakkam, India. The Indira Gandhi Center for Atomic Research (IGCAR) and Bhabha Atomic Research Centre (BARC) jointly designed, constructed, and operate the reactor. The reactor was designed to produce 40 MW of thermal power and 13.2 MW of electrical power. The initial nuclear fuel core used in the FBTR consisted of approximately 50 kg of weapons-grade plutonium. The reactor uses a plutonium-uranium mixed carbide fuel and liquid sodium as a coolant. The fuel is an indigenous mix of 70 percent plutonium carbide and 30 percent uranium carbide. Plutonium for the fuel is extracted from irradiated fuel in the Madras power reactors and reprocessed in Tarapur.
Some of the uranium is created from the transmutation of thorium bundles that are also placed in the core. Using the experience gained from the operation of the FBTR, a 500 MWe Prototype Fast Breeder Reactor (PFBR) is in advanced stage of construction at Kalpakkam. |
Commercial reactors and power generation
Pressurized heavy-water reactors
BARC has developed various sizes of
The IPHWR class was developed from the
Advanced heavy-water reactor
BARC is developing a 300 MWe
Indian molten salt breeder reactor
The Indian molten salt breeder reactor (IMSBR) is the platform to burn thorium as part of 3rd stage of Indian nuclear power programme. The fuel in IMSBR is in the form of a continuously circulating molten fluoride salt which flows through heat exchangers for ultimately transferring heat for power production to Super-critical CO2 based Brayton cycle (SCBC) so as to have larger energy conversion ratio as compared to existing power conversion cycle. Because of the fluid fuel, online reprocessing is possible, extracting the 233Pa (formed in conversion chain of 232Th to 233U) and allowing it to decay to 233U outside the core, thus making it possible to breed even in thermal neutron spectrum. Hence IMSBR can operate in self sustaining 233U-Th fuel cycle. Additionally, being a thermal reactor, the 233U requirement is lower (as compared to fast spectrum), thus allowing higher deployment potential.[39]
Light-water reactors
BARC with experience gained from the development of the light-water reactor for the Arihant-class submarine is developing a large 900 MWe pressurized water reactor design known as IPWR-900. The design will include Generation III+ safety features like Passive Decay Heat Removal System, Emergency Core Cooling System (ECCS), Corium Retention and Core Catcher System.
BARC has developed multiple designs of light-water reactor designs suitable for nuclear marine propulsion for Indian Navy submarines beginning with the CLWR-B1 reactor design for the Arihant-class submarine.Total four submarine will be built for this class.
India and the NPT
India is not a part of the
More recently, India and the United States signed an agreement to enhance nuclear cooperation between the two countries, and for India to participate in an international consortium on fusion research, ITER (International Thermonuclear Experimental Reactor).[42][43]
Civilian research
The BARC also researches biotechnology at the Gamma Gardens and has developed numerous disease-resistant and high-yielding crop varieties, particularly groundnuts. It also conducts research in Liquid Metal Magnetohydrodynamics for power generation.
On 4 June 2005, intending to encourage research in basic sciences, BARC started the Homi Bhabha National Institute. Research institutions affiliated to BARC(Bhabha Atomic Research Centre) include IGCAR (Indira Gandhi Centre for Atomic Research), RRCAT (Raja Ramanna Centre for Advanced Technology), and VECC (Variable Energy Cyclotron Centre).
Power projects that have benefited from BARC expertise but which fall under the NPCIL (
The Bhabha Atomic Research Centre in addition to its nuclear research mandate also conducts research in other high technology areas like accelerators, micro electron beams, materials design, supercomputers, and computer vision among the few. The BARC has dedicated departments for these specialized fields. BARC has designed and developed, for its own use an infrastructure of supercomputers, Anupam using state of the art technology.
See also
- IPHWR, class of PHWR electricity generation reactors designed by BARC
- AHWR, thorium fuelled reactor being designed by BARC
- Milw0rm#BARC attack
- Department of Atomic Energy, Government of India
- Indira Gandhi Centre for Atomic Research
- Raja Ramanna Centre for Advanced Technology
- Variable Energy Cyclotron Centre
- Homi Bhabha Cancer Hospital and Research Centre (disambiguation)
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