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62nd Republic Day of India
26th January (Wednesday), 2011
09:00 hrs
Address by
Dr. Ratan Kumar Sinha
Director, BARC
My greetings to all of you on the occasion of the 62nd Republic Day of our country. As all of you know, in the year 1950, the Constitution of the sovereign democratic republic of India was adopted and world’s largest democracy was born.
Every year, as a part of this celebration, we salute our national flag. We also remember and salute the members of our armed forces, who provide security to our country.
This function provides us an opportunity to take stock of our achievements during the year. The programmes of our Organisation of more than 15,000 colleagues are extremely diverse and voluminous. Therefore, on this occasion today, I intend to cover only a few representative activities, providing a glimpse of our achievements during the recent past.
Research Reactors
As all of you are aware, last year, two of the research reactors Canadian Indian Reactor (CIRUS) and Dhruva have successfully completed 50 years and 25 years of very productive operation. CIRUS continued to operate at an availability factor of around 87% until December 31, 2010, when the reactor was permanently shut down.
As a part of upgrading the core of the Apsara reactor, decommissioning activities of the reactor and reactor systems have already been completed. Demolition of the existing reactor building will commence soon to enable construction of the new building. Detailed engineering of various reactor systems of upgraded Apsara is currently in progress.
Research reactor Dhruva has also been taken up for refurbishment and replacement of various equipment and components to ensure its continued high availability.
The Advanced Heavy Water Reactor (AHWR) Critical Facility was operated for various experiments. A mixed pin cluster carrying thorium oxide as well as natural uranium pins was loaded in four different locations of the AHWR Critical Facility. Criticality was achieved with all these loadings and the observed critical height was in close agreement with the estimated critical height. Multiple foils were irradiated to obtain the reaction rates in various energy regions and SAND-II code was used for the spectrum unfolding.
Testing of nuclear detectors in graphite reflector region continued. Moderator level coefficient
measurements were carried out and observed values matched with predicted ones. Reactivity measurement due to loading of a cluster containing Thoria and Uranium pins was carried out satisfactorily. Facility was also utilised for large volume sample irradiations for Neutron Activation Analysis (NAA).
The conceptual design of a High Flux Research Reactor (HFRR) to be built at our new campus at Vizag, has been completed. HFRR is designed primarily to meet the large requirements of high specific activity radio-isotopes and to provide enhanced facilities for basic research in frontier areas of science and for applied research related to development and testing of nuclear fuel and reactor materials.
Advanced Heavy Water Reactor (AHWR)
The AHWR Thermal hydraulic Test Facility (ATTF) is being setup at R&D Center, Tarapur, in collaboration with Nuclear Power Corporation of India Ltd. (NPCIL), to establish thermal and stability margins as well as to test the fuelling machine at prototypical conditions. The various work modules of the project like civil, mechanical, electrical, instrumentation and control are at an advanced stage of execution.
Thermal hydraulic analysis of AHWR with Low Enriched Uranium (LEU) was carried out to estimate the thermal margin. It was found that adequate thermal margin exists with LEU in the AHWR core. A feasibility study was also carried out for the power uprating of AHWR using pumped circulation with LEU.
In order to reduce the plutonium requirements of the AHWR initial core, various options of partial loading of AHWR initial core were studied. Detailed studies related to AHWR equilibrium core with Th-LEU fuel for a target burnup of 60 GWd/te were carried out. An initial core with LEU fuel has been designed with desirable operational features during refueling and transition to the equilibrium core.
The design of the secondary shut down system of AHWR was modified to have eight injection tubes at two elevations. The jet dynamics was modeled using an indigenously developed methodology and the worths were estimated.
Compact High Temperature Reactor (CHTR) and 600 MWth High Temperature Reactor (HTR) for Hydrogen Production
Solid modeling of CHTR systems and components was completed. CHTR fuel rod simulator costing about 1% of the imported option was developed. Fabrication of molten salt loop and corrosion test facility for high temperature reactor application has been completed.
The challenging task of treating the double heterogeneity effect created by lumping the fuel into particles and those into pebbles has been done using the Reactivity equivalent Physical Transform (RPT) method. The results were compared with reference results from Monte Carlo simulation of a pebble, in which double heterogeneity has been treated explicitly.
CHTR physics design simulations were performed with new design modifications such as use of thinner control rods for finer control, Reduction in the available locations (18 to 12) for control rod etc. Efforts were made to minimise the single CR worth at criticality by varying the content of burnable poison.
Study of Thorium utilisation in Pressurised Water Reactors
A study of possibility of thorium utilisation in a Pressurised Water Reactor (PWR) was made by considering the (Th-LEU (19.75% U-235))MOX fuel. PWR cores fuelled with thorium using different fissile compositions were studied.
LWR studies
An updated WIMS library in 172 groups has been generated in-house with burn-up chain extended up to 252Cf. This library contains 185 nuclides and resonance integral tabulation for 48 resonant nuclides, including several minor actinides with temperature extended up to 2500K. This library has performed successfully for the VVER simulations.
Fuel development and supply
BARC has the responsibility of supplying plutonium bearing fuels for the Fast Reactor Programme, including Fast Breeder Test Reactor (FBTR) and Prototype Fast Breeder Reactor (PFBR) (under construction) at Kalpakkam.
For the production of U-Pu mixed carbide fuel pins for FBTR, new technologies like Laser welding for the fuel pin end-plug closure and Laser engraving unit for fuel pin numbering have been qualified and are being inducted into the production line.
The regular production of Mixed Oxide (MOX) fuel pins for PFBR has started at Advanced Fuel Fabrication Facility (AFFF) and a new fuel pin welding line has been recently commissioned. The experimental PFBR MOX fuel being irradiated at FBTR has now reached a burn-up of 107,000 MWd/T, exceeding the design target burn-up of 100,000 MWd/T.
BARC is also involved in R&D on metallic fuel for the advanced fast breeder reactors with high breeding ratio. Thermophysical properties like phase transition temperatures, solidus temperature and eutectic temperature between U-15%Pu fuel and T-91 cladding has been determined. A glove box train consisting of injection casting, demoulding and eddy current inspection of fuel slugs has been set up at Atomic Fuels Division (AFD).
For the AHWR Fuel Fabrication mock-up facility project, radiation resistance remote viewing system has been developed indigenously for hot cell and shielded enclosure applications for AHWR fuel fabrication.
Based on the post irradiation examination of the thoria-4%plutonia mixed oxide fuel elements, two of the intact fuel elements were certified to be fit for re-irradiation in CIRUS reactor. These two fuel elements, along with fresh fuel elements containing thoria-8%plutonia of AHWR fuel design, manufactured at AFFF, were reconstituted into an irradiation rig and loaded into CIRUS for irradiation. This exercise has helped us to arrive at the procedure for quality assurance for reloading and re-irradiation of experimental fuels in the test loops of research reactor. Both the irradiated pins, despite being cooled for more than twelve years in the spent fuel storage pool, could withstand the irradiation, till the closure of the CIRUS.
Neutron radiography set-up for irradiated fuel pin at CIRUS was installed and commissioned. After trial runs with unirradiated fuel pin, neutron radiography of irradiated Pressurised Heavy Water Reactor (PHWR) fuel pin and experimental thoria-plutonia MOX fuel pins were carried out. Defects like, fuel cracks, hydriding of clad, and swelling and dislocation of fuel were detected. Details of fuel pin like pellet gap, spring inside the pin at the end were also clearly visible in the neutron radiograph. Decrease in fuel column length was observed in the experimental thoria-plutonia fuel pins having low density pellets. Formation of central void was found in experimental thoria-plutonia MOX high burnup fuel pin.
Detailed post-irradiation examination has been carried out on Zr-2.5Nb-0.5Cu loose fit garter springs, taken out from 10 high flux channels, five each from Kakrapar Atomic Power Station-1 (KAPS-1) and Narora Atomic Power Station-1 (NAPS-1) PHWR reactors. These garter springs were retrieved during the EMCCR operation after around 10.5 Effective Full Power Year (EFPY) of operation.
An indigenous micro-wave heating system (1-6 kW power), adapted and retrofitted to existing hot-cell (without any alteration), was tested. It will be used for the dissolution of irradiated thoria based fuels and materials and also for actinide separation studies of advanced fuels.
Reprocessing and Waste Management
Reprocessing plants at Trombay and Kalpakkam continued to operate safely and satisfactorily. Radioactive wastes generated from nuclear installations both at Trombay & Kalpakkam were managed safely. In addition, during the year, radioactive wastes generated during partial decommissioning of Apsara was managed quite efficiently.
The development of oblong-shaped metallic melter to achieve higher through-put in waste vitrification process was completed and the unit was commissioned.
As a part of automation programme for plutonium reconversion laboratory, extensive trial runs were taken on rotary vacuum drum filter and continuous screw calciner. Automation of reconversion laboratory, besides increasing the through-put, helps in bringing down the load on operator and man-rem expenditure.
Towards deep geological repository programme, developmental activities were continued. Setting up of an underground research laboratory has been initiated. This laboratory will facilitate conducting various experiments under inactive conditions, such as studying the effect of vitrified waste canister on the host rock, its remote handling aspects, validation of codes for migration of various radio-nuclides, etc.
An incinerator for radioactive solid waste at Radioactive Solid Waste Management Site (RSMS), BARC, Trombay has been refurbished and commissioned. A volume reduction factor of hundred was achieved and the airborne activity during the incineration was below detection limit, indicating effectiveness of air treatment system.
Installation and testing of Resin Fixation Facility for conditioning of spent resins in polymer matrix is nearing completion at RSMS, Trombay. The facility has incorporated the process for immobilisation of spent resins in specific cement also.
At Centralised Waste Management Facility (CWMF), Kalpakkam, a new facility for retrieval, volume reduction and disposal of stored pressure tubes has been designed and a work order has been released after obtaining necessary safety clearances. A facility for melt densification has been in continuous use for treatment of plastic/polythene waste. Based upon the experience gained from the facility, a new scaled up facility with certain modification is being set up.
Feasibility studies have been initiated for vitrification of High Level Waste (HLW) from AHWR and Fast Reactor Fuel Cycle Facility (FRFCF) in sodium borosilicate glass matrix. Irradiation of typical sodium borosilicate glass composition to study long term radiation stability of glass matrix with respect to alpha radiation and recoil damage has been completed. Thermal property of acid and molten glass resistant refractory material has been enhanced by addition of bubble alumina.
Further development work is in progress for Cold Crucible Induction Melting technology for vitrification of HLW. Green heating experiments have been carried out successfully. Model-based design of cold crucible for hull melt densification has been completed.
Separation of useful isotopes such as 106Ru, 90Y etc. was continued for supplying these materials for medicinal use. Techniques for quality control of the recovered 90Y were also developed.
An underground research laboratory is being set up in one of the captive sites of the Department. This laboratory will help in conducting various experiments such as study of the effect of heat generating canister on the disposal environment, development of methodologies for emplacement/retrieval of the canister remotely, validation of various codes for predicting the migration of activity, mechanical stresses in the host rock due to the digging of the tunnel etc.
Health, Safety and Environment
Environmental Studies
Environmental surveys for the baseline studies of the new uranium mining projects at Tummalapalle (A.P.) and new BARC campus at Vizag are currently in progress. Pre-operational survey at new Nuclear Power Plant sites of Hissar in Haryana and Mithivirdi in Gujarat were also initiated.
Studies on assessment of radiological impact of the proposed uranium tailings pond at Seripalli in Nalgonda district of Andhra Pradesh have concluded that the radiological impact of the proposed uranium tailings pond is trivial up to a period of 2000 years and will be of no concern after this period.
A cone beam optical computed tomography (CBOCT) system has been designed, developed and tested for obtaining 3-D dose distribution from advanced radiotherapy equipment using polymer gel dosimeter. The facility for preparing polymer gel dosimeter has also been established. The system will be useful for dose verification in radiotherapy.
There was a need for dosimeters in the dose range of 100 to 1000 Gy for low dose applications of food irradiation, especially for mango irradiation. Accordingly, two new dosimeters were developed in the dose range mentioned using i) Glycine & (ii) Lithium formate. These systems being indigenously developed are cost-effective.
Analysis of the data on the effect of radiation on congenital malformations, such as mental retardation (MR) and cleft lip/palate (CLP), using case control methodology, generated under the three year epidemiological study project, has been completed. The results indicate no statistically significant excess relative risks for the occurrence of these malformations attributable to natural background radiation.
Safety studies
BARCOM Test Model for Ultimate Load Capacity Assessment
The 1:4 size BARC Containment (BARCOM) Test Model simulating the 540 MWe PHWR inner containment was subjected to over-pressure test till the first appearance of crack was realised. This occurred at a pressure of 0.2207 MPs, which is 1.56 times its design pressure. The failure initiation was attributed to inelastic strains developed in the discontinuity regions of Main Air Lock and Emergency Air Lock. The data collected during the pressurisation has been compared with analytical predictions reported by various International Round Robin Participants, including that of in-house code ULCA from BARC.
Cyclic Fracture Tests on Narrow Gap Welded (NGW) SS304LN Stainless Steel Pipes
Cyclic fracture tests were conducted to address the concern about the effect of cyclic loading anticipated during a seismic event. Apart from pipes with cracks in base metal; conventionally welded pipes using Submerged Metal Arc Welding (SMAW) and those welded using Hot Wire Pulsed Gas Tungsten Arc Welding (GTAW), with narrow gap were also tested. The investigation has revealed that the Cyclic Tearing and monotonic fracture resistance of narrow gap GTAW is superior to SMAW, supplementing the other advantages of GTAW, such as lower residual stress and reduced susceptibility to sensitisation.
A supercritical test facility was set up earlier to investigate heat transfer, pressure drop and stability behaviour of supercritical fluids. The facility was earlier operated with supercritical carbon-dioxide up to 90 bar pressure. The facility was modified for operation with Supercritical Water (SCW) up to 250 bars and 400 oC and experiments are going on.
Channel Heat up Studies for PHWR
Pressure Tube is expected to have a circumferential temperature gradient during flow stratification for a small break Loss of Coolant Accident (LOCA) situation in a PHWR. A trial experiment for asymmetric heating (circumferential) of pressure tube for 220 MWe PHWR at atmospheric pressure has been carried out with a 19 Fuel Pin Simulator.
Seismic Qualification of glove boxes
The seismic qualification tests were performed on different configurations of glove boxes viz. single glove box, glove box train and double module glove box. The studies concluded that the glove boxes could safely withstand a ground acceleration of 0.2 g. Necessary modifications have been identified, which would enable them to withstand higher acceleration.
AHWR safety
As a part of demonstration of safety margins available in AHWR, analyses were carried out to identify plant symptoms generated during Beyond Design Basis Event for “decrease in inventory” category. It was shown that, even for the scenario involving a 200% break at inlet header along with un-availability of Emergency core Cooling System (ECCS) and loss of moderator as a heat sink, symptoms can be identified and sufficient time is available for well defined operator action to prevent fuel temperature excursion.
Physics
CIRUS Reactor has been used for neutron tomography of hydrogen blister in Zircaloy and for neutron based phase contrast imaging of substances embedded inside dense material.
A high power/high energy Nd:Glass laser system of 20 joules and pulse width 300 – 800 pico second with focusable intensity better than 5 x 1014 watts/cm2 has been indigenously developed. This laser system has been used to generate shock pressure exceeding 25 Mega bar in several materials.
The performance of the indigenously developed Folded Tandem Ion Accelerator (FOTIA) has been steadily improving. Recently, the proton beam current from this accelerator has reached a high value of 2 micro amp, one of the best values one can get from a low energy accelerator of this type.
Materials and metallurgy
A process for the separation of rare earths comprising of yttrium as major constituent, along with erbium, holmium, ytterbium as minor components from merchant grade phosphoric acid, employing DNPPA+TOPO as synergistic extractant mixture, was developed by selective scrubbing with 40% sulphuric acid. The scrub solution was further subjected to sodium double sulphate precipitation, followed by re-dissolution and oxalate precipitation and conversion to oxide. The rare earth product was purified to > 99%, with respect to sodium by digesting with hot water. Counter-current tests showed overall 90% recovery.
Production of U-metal ingots was continued and utilised for fuel fabrication for research reactors, proposed Sub-cirtical Facility at Purnima and specific requirements at Metallif Fuels Division (MFD).
Development of tubular solid oxide fuel cell (T SOFC)
Process has been established to fabricate single SOFC cell of tubular configuration (both in anode and cathode supported ) through co-isostatic pressing followed by co-firing. Anode supported cell was found to give a maximum of 62 mW.cm-2 power density when tested at 900 oC. Work is in progress to improve the performance by addressing the issues related to fuel distribution, sealing and current collection of SOFC cell.
Development of catalyst material for decomposition of sulphuric acid in I-S processes for hydrogen production
A process has been developed for bulk preparation of iron oxide based catalyst pebbles for use in the decomposition of sulphuric acid in I-S processes for hydrogen production. The catalyst showed high (~78%) yield for conversion of H2SO4 to SO2 with long run stability. Bulk preparation is under progress for carrying out pilot test in Chemical Technology Division
The stress corrosion crack growth rates in AHWR simulated high purity water at 288 degree C in a recirculating test facility have been successfully established on the materials proposed to be used in AHWR. SS 304L with addition of 0.08 and 0.16 wt% nitrogen were used in sensitized condition and also in as – received materials with 20% warm working (non-sensitised) conditions. These results on our materials to be used in AHWR provide important inputs about crack growth behaviour of the materials.
Stainless steels have been proton irradiated at FOTIA and at PELLETRON at 4.8 MeV and at a temperature of 300 degree C. The Radiation Induced Segregation (RIS) has been successfully characterised using a new approach of electrochemical and atomic force microscopic characterisation.
Lasers and Accelerators
10 MeV Linear Accelerator (Linac):
The depth dose distribution of the electron beam of the 10 MeV RF linear electron accelerator were measured using B3 Radiochromic films. The electron beam has been employed for demonstrating industrial applications towards cross-linking of poly-ethylene rings (more than 1 lakh pieces), diamond coloration, Teflon degradation and production of photoneutrons.
BARC- ECIL RF LINAC:
The 9 MeV cargo scanning RF Linac was operated with beam parameters of 9 MeV, 60 mA, 7 microsecond duration at 250 Hz pulse repetition rate. Experiments on electron beam transport and beam focusing at X-ray target were carried out. X-ray spot size of 2.5 mm diameter on the target and a dose of 24 Gy/minute at 1 meter from the target was measured. The X-ray collimator has been developed and installed.
AVLIS programme
The knowledge of the velocity of atomic beam and thermal ion content is important in various processes involved in our AVLIS programme. The experimental measurements of atomic flux, flow velocity and thermal ion content were carried into a 100kW zirconium evaporator using micro-balance and Langmuir probes. The measurements carried out up to 3270 K at a height of 400 mm were compared with the estimated values for the thermal velocity, terminal Mach number velocity and velocity due to internal conversion of energy from meta-stable energy levels upto 5000cm-1 into kinetic energy.
Demonstration of narrow CPT Resonance
As a part of the ongoing programme on generating an ultra precision frequency reference for atomic clock, a coherent population trapping signal with a width of 14 KHz was achieved through use of a special vertical cavity laser with RF modulation and side band generation.
Test Blanket Module (TBM) development for ITER programme
As a part of Test Blanket Module development for Indian ITER programme, joint MHD experiments at high magnetic fields with BARC-IPR Test-sections at Institute of Physics, University of Latvia (IPUL) have commenced and experimental test-sections made of austenitic steels have been tested.
Development of 15 kV,6 kW Electron Beam Melting Machine
An indigenous 15 kV, 6 kW Electron beam melting machine was designed and developed. This computer controlled machine will be used for production of high purity Uranium and Thorium alloys in the form of buttons, rings and fingers by EB melting and consolidation.
DM&AG
An Autonomous Guided Vehicle (AGV) based Material Transfer System has been developed, which can be used in manufacturing environments for autonomous transfer or distribution of materials from a supply point to several machining shops. The same solution can also be used for unmanned transfer of radioactive materials in nuclear installations like Board of Radiation & Isotope Technology (BRIT), Nuclear Fuel Complex (NFC), etc. The system autonomously monitors stock levels at the delivery points and initiates appropriate transfers to maintain uniform satisfaction at all delivery points.
ChTG/RMP
Design, development and manufacturing of a prototype batch of Micro Electro Mechanical Systems (MEMS) based pressure and opto-mechanical pressure sensors using micro-nano engineering technology has been successfully completed.
With the successful criticality crossing of a prototype Advanced Multi-section metallic High Speed Rotor, capacity of producing the separative output of the existing machines will be doubled.
About 1800 acres of land in Challekere Taluk of Chitradurga District has been acquired for setting up of Special Material Facility during the XII Plan.
Prototype Tritium monitors based on Bremsstrahlung technique have been successfully developed.
Computational Analysis Division
A five (5) Teraflop High Performance Computing Facility has been set up at the Facility for Electromagnetic Systems (FEMS), BARC, Visakhapatnam. A variety of in-house codes have been parallelized for efficient use of this system. By end-2011, it is proposed to upgrade this to a 20 Teraflop system.
An electromagnetic coil-gun, accelerating metallic projectiles weighing 30-50 grams to velocities upto 100 meters/sec, has been set up and in regular operation. A 2-D MHD computer code, developed in-house for modelling this gun, has yielded good agreement with experiments, and is being used for optimization. The gun, which yields reproducible results, will be used for studying high velocity impact and penetration phenomena.
Development of Instrumented and Caliper Pipe Inspection Gauges (PIGs)
In continuation with the development of instrumented pigs and caliper pigs for in-line inspection of pipelines, tools for 24” nominal bore pipelines have been integrated and delivered to Indian Oil Corporation (IOC). They are tested in wet evaluation facility of IOC R&D Centre, Faridabad. The instruments use state-of-the-art digital signal processing (DSP) electronics for acquisition and on-line processing of magnetic flux leakage data. 12” instrumented PIG developed earlier is upgraded and successfully run for 200 km of Allahabad-Kanpur section of IOC pipeline. The defect report has been used for repairing severe defects.
Basic Research in Chemistry
An indigenous synthesis of the ligand, MIBI has been developed and used successfully for the preparation of the heart imaging agent, Tc-MIBI complex. Following the approval by the Radiopharmaceutical Committee, the product is currently being marketed by BRIT and supplied to the hospitals of Maharashtra. This is an import substitute and has reduced the cost of the medicine drastically.
A new pyromethene (PM) laser dye, with significantly improved photo-chemical stability than the commercially available dye has been designed. The new dye shows similar lasing efficacy as that of the commercial one, and is currently being considered for use in the U-enrichment programme.
Using Microwave Plasma Chemical Vapour Deposition (CVD) technique, high quality and highly oriented CVD diamond thin films were grown on silicon wafer (1-5 cm2 area) to make alpha detectors, configured in the form of metal-insulator-semiconductor hetero-structure. The detectors were successfully tested for alpha sensitivity in air, using electroplated 238Pu source.
A granular biofilm based process for denitrification of high strength nitrate-bearing effluents generated in the nuclear industry has been developed. Denitrification of upto 12,000 mg/l nitrate was achieved in lab scale bio-reactors. Effluent nitrate/nitrite levels at the end of 24 h cycle time were less than 10 mg/l, which can be safely discharged to the environment.
A biological process is under development for the removal of sulphate from sulphate-bearing barren effluents, such as those produced at Uranium Corporation of India Ltd. (UCIL), Jaduguda. In this method, a series of three bio-reactors employing sulphate reducing bacteria was used to sequentially bring down sulphate concentration from 18,000 ppm to below 100 ppm. Experiments are being conducted to reduce operational cost by making use of cheap carbon sources for the growth of the SRB.
A fuel cell based hydrogen burner has been developed for burning the deuterium formed during chemical decontamination and the deuterium formed in stoichiometric excess in the moderator cover gas during normal operation. The method consists of a fuel cell and a heated palladium catalyst column as pre-treatment facility for removing oxygen from deuterium. The catalyst column ensures the removal of oxygen from deuterium and the pure deuterium coming from the catalyst column is allowed to pass through the fuel cell, where it combines with oxygen to form D2O.
Nuclear Agriculture
A new mungbean variety TM-2000-2 (Pairy mung) with early maturity and disease resistance, suitable for rabi and utera (rice fallow) cultivation conditions has been released and notified for Chhattisgarh State. The total number of Trombay crop varieties released and notified by Ministry of Agriculture, Government of India for commercial cultivation has now reached 39.
In groundnut, two simple sequence repeat (SSR) markers were found to be tightly linked with rust resistance gene for use in marker assisted breeding.
Rainwater harvesting facility was developed at agricultural farm of Nuclear Agriculture & Bio-Technology Division (NABTD), BARC, Gauribidanur for breeder and nucleus seed production.
45 Nisargaruna solid waste treatment plants were established in various places in the country under the guidance from BARC.
Technology Transfer and (Advanced Knowledge and Rural Technology Implementation) (AKRUTI) programme
Besides filing 3 international patents, and one national patent based on in-house R&D activities, seven new technologies in the area of safe drinking water, one in medical electronics and one in solid waste management were transferred to industry successfully.
As a part of development of BARC Centre for Incubation of Technology (BARCIT), civil, electrical, air-conditioning work at the five Technology Incubation Cells are in advanced stages of completion and are likely to start the operation by March 2011, under Phase I of the operation of BARCIT.
Among the ten MoUs signed with different organisations during the year, commercial use of KRUSHAK Irradiator, Lasalgaon by Maharashtra State Agriculture and Marketing Board (Pune) and Barge Mounted Sea Water Reverse Osmosis Plant for Production of Drinking Water, by IREL are noteworthy.
BARC has signed seven AKRUTI Tech Pack agreements for deployment of technologies in rural sector. These include four private companies, 2 NGOS and one woman entrepreneur. Tissue Culture Laboratory at AKRUTI-CARD (Centre for Appropriate Rural Development) in Anjangaon-Surji, Amravati has become operational.
Isotope Hydrology based identification of bore well location has been successfully implemented in AKRUTI-CARD (Community Action for Rural Development), Amaravati in a water scarce area. The farmers were asked to drill borehole about 60 m deep at the identified site at Anjangaon village, Amravati district, Maharashtra. The borehole is now yielding ~30,000 Litres of water per hour and is a perennial source of good quality drinking water for 5- 6 villages. Encouraged by the success of the model project, six more projects are underway.
Medical Services
As you all know, our BARC hospital, along with its 12 zonal dispensaries caters to more than 87,000 registered beneficiaries, While every effort is being made to improve our on-line services, two new machines viz., Radial Fluro X-ray machine and Computerised Radiography System have been installed and are being used for needy patients. The newly renovated ward 4A is now made available, along with 18 normal beds, 6 air conditioned beds and 14 emergency beds to the patients. It is also proposed to introduce new dispensary at Kharghar, Navi Mumbai for the convenience of the beneficiaries of Navi Mumbai. Land for this dispensary has already been occupied, and further work is under progress. It will take 3 years for full functioning of this dispensary.
A multiplex polymerase chain reaction (PCR) protocol, involving two genes for detection of tuberculosis, was standardised and validated. It has been given to BRIT for the formulation of a TB detection kit and its commercialisation
177-Lu labeled dotatate synthesised in-house is being used for radiotherapy of neuroendocrine tumors at RMC. With the installation of a new Dual Head Gamma Camera, it has become possible to handle more number of cancer patients in RMC now.
XI Plan activities :
We are shortly coming to the close of our XIth plan project activities. In order to formulate our programmes for the XIIth plan project, it is essential to critically review our progress and judiciously extrapolate to decide about closing the projects or, if necessary, continuing under the next plan. This process is currently on through various group Boards. Based on the outcome of this activity, we will be in a position to put up new programmes under the next plan. I earnestly appeal to all of you to timely contribute to this process.
Physical Protection
Physical protection of our Centre and its various installations is of paramount importance. I am sure, all my colleagues will understand that the concern of security has further increased in the present time. I strongly urge our Fire Service personnel to maintain a constant vigil on the various establishments of our centre and strive to improve their coordination with security and the concerned Divisions.
I also compliment all officers and staff of our Centre for extending their cooperation with the security personnel in discharging their duties effectively for implementing the higher level of security procedures. Finally, I urge all my colleagues in our Centre to remain vigilant and alert in the present environment.
The contribution made by the personnel of our Landscape & Cosmetics Maintenance Section is aptly demonstrated by the beautiful ambience of this venue.
Conclusion
My dear colleagues, on one hand, we have committed ourselves to be at the frontiers of science and technology at international level. On the other hand, we also have a commitment to provide benefits of our knowledge and technologies to the Indian society at large, at all levels. You may know very well that it has been our mandate to develop national capability in all areas associated with nuclear sciences and technologies and our fulfillment of this mandate, inspite of an embargo regime, has been the key to make us strong enough to acquire a pronounced international stature. This spirit of self-reliance and development of indigenous solutions must continue. Currently, we are in the process of formulating our ideas for the XII Five Year Plan period. Let us carry out a rigorous analysis of any residual gaps and vulnerabilities and formulate projects and activities to bridge the gaps indigenously.
I am sure, all of you will continue to put in your efforts so as to sustain our tradition of excellence in the years to come.
Friends, therefore, on this very special day, let us firmly resolve and rededicate ourselves to continue our pursuit of excellence in the frontier areas of nuclear science and technology for the betterment of life of our people.
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