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Abstract: Carbon capture and storage (CCS) might be an important climate protection technology for coal-rich countries. This paper presents first results of a systemic and long-term analysis of a future CCS implementation in India. It focuses on potential storage formations in the geological subsurface and the geographic match of these sinks with CO2 emissions of current and future largepoint power plants. The analysis is framed by an overview on India’s position on CCS, ongoing Indian research and development projects as well as its international activities. The geological potential for CO2 sequestration in India is subject to large uncertainty because, so far, only few studies estimated it in a vague manner. A first meta-analysis shows that there is a huge variation between 48 Gt and 572 Gt of CO2. The main differences between the evaluated studies are the assumed capacities for deep saline aquifers and basalt formations. Taking the ongoing discussion and the existing uncertainties into account, the storage potential might be provided only by aquifers (in the range of 44 to 360 Gt of CO2) and hydrocarbon fields (2 to 7 Gt of CO2). The amount of CO2 emissions possibly available for sequestration is assessed by applying three substantially different long-term energy scenarios for India. These scenarios, indicating pathways between a ”low carbon” and a ”high carbon” development until 2050, result in cumulated CO2 emissions between 30 and 171 Gt if all new large-scaled power plants will be based on CCS from 2020 on. Compared with the sink capacities, only the CO2 emissions of scenario S2 (30 Gt) could theoretically be stored with high certainty. Considering the scenarios S3 and S1, their CO2 emissions (94 Gt and 171 Gt, respectively) could only be sequestered if the aquifer capacity would prove to be usable. Geological storage sites do not appear to be located close to sources in South West, Central, North and North East India. This first rough analysis means that only those CO2 emissions occurring in the Western parts of North and West India, the Eastern part of South India as well as the South part of East India might be suited for sequestration nearby. A more detailed source-sink matching will follow in the next phase of the project, including results of expert meetings in India. Furthermore, this analysis will be complemented by an additional assessment from economic, ecological and resource-strategic points of view, which might further affect the potential for CCS. [Copyright &y& Elsevier]

Abstract: This paper presents an overview of the current status of the main CCS initiatives in the major emerging economies: China, India, Brazil, Mexico, Russia, and South Africa. This study first covers all six countries as a group and describes their natural resources. The second part of this study embraces each country individually and includes current initiatives and current legal and technological status of CCS. At the end, this study summarizes the main findings in the emerging economies and the potential of including CCS as part of the CDM. [Copyright &y& Elsevier]

Abstract: In the Indian energy scenario projections for the future, the nuclear power through fast reactors is expected to play an important role of ∼ 20% of total installed capacity by 2052. Successful operation of 40 MWt/13 MWe capacity Fast Breeder Test Reactor(FBTR) since 1985, strong R&D executed in multidisciplinary domain backed up by manufacturing technology and construction of 500 MWe Prototype Fast Breeder Reactor (PFBR) based on indigenous design have provided high confidence on the success of sodium cooled fast reactor technology. PFBR is a pool type MoX fuelled reactor designed with 2 primary sodium pumps, 2 secondary loops, 8 single wall integrated once through steam generators, and a rectangular containment. PFBR is presently under advanced stage of construction. Beyond PFBR, it is planned to construct 6 more FBRs of 500 MWe capacity each. Towards this, a systematic roadmap has been drawn for improved economy and enhanced safety through a number of measures. Roadmap for necessary R&D and manufacturing technology has been well detailed. The major features incorporated are twin unit concept, plant life increased to 60 years in comparison to 40 years for PFBR, reduction in number of steam generators from 8 to 6, reduction in special steel specific weight requirements, integrated primary sodium purification, enhanced reliability of shutdown systems, enhanced diversity in decay heat removal systems, enhanced in -service inspection, and compact plant layout. Beyond 2025, a series of 1000 MWe capacity metallic fuel with higher breeding potential are planned. R&D activities have been systematically formulated for metallic fuel development of both sodium bonded and mechanical bonded design. The paper addresses the highlights of current operating experience of FBTR and its life extension, construction status of PFBR, and design features of future sodium cooled fast reactors in India. [Copyright &y& Elsevier]

Abstract: When examined from the point of view of the size of its population and economy, India is not well endowed with energy resources. Studies done by the Department of Atomic Energy indicate that even after exploiting full potential of every available source of energy including nuclear energy, India needs to continue to import energy resources. In this backdrop, an initiative was launched by Government of India to open up international civil nuclear commerce so as to enable India to access natural uranium from international market and to set up nuclear reactors in technical cooperation with other countries. The paper provides details of what has been done so far, ongoing steps and likely growth scenario for nuclear installed capacity in the country. [Copyright &y& Elsevier]

Abstract: The three stage Indian nuclear power programme envisages efficient use of its modest uranium resources and full exploitation of its vast Thorium resources. Indian economy is on a fast growth track. The growth in population and economy is creating huge demand for energy which has to be met with environmentally benign technologies. Nuclear Energy is best suited to meet this demand without causing undue environmental impact. In view of limited resources of Uranium and vast resources of Thorium, a closed fuel cycle to fully exploit the potential of the two resources is co nsidered essential. In conformity with such a strategy, Recycle fuel fabrication technologies have been under development in India for over three decades. Some of the activities such as (i) Fabrication and development of MOX fuels for LWRs/PHWRS (ii) Fabrication of mixed carbide and mixed oxide fuels for Fast Reactors (iii) Research and development in Metallic Fuels for Fast Reactors and (iv) Development of fuels for Thorium utilization - are briefly discussed in the paper. [Copyright &y& Elsevier]

Abstract: Presently the installed capacity of electricity generation in India is 160 GWe. The integrated ene rgy policy aims at an installed capacity of 778 GWe by 2031-32 to achieve per capita electricity consumption of 2700 kWh/year as against the 700 kWh/year. The share of nuclear power in India is around 3% presently. The increase in installed capacity is possible by increasing the share of nuclear power. India has opted for a unique three-stage power programme based on closed nuclear fuel cycle, which provides a multiplier effect through breeding. Consequent to the 123 agreement and clearance from Nuclear Supplier‟s Group (NSG) for international cooperation in the field of nuclear energy, the reactor technology options are wide open. Some of the technologies which are being pursued are: Pressurized Heavy Water Reactors (PHWRs) fueled with domestic Natural Uranium (NU), PHWRs fueled with imported Natural Uranium/Slightly Enriched Uranium (SEU), Light Water Reactors (LWRs) procured from abroad using imported Lightly Enriched Uranium (LEU) fuel, PHWRs with Reprocessed Uranium (RU) obtained from reprocessing spent fuel of LWRs, indigenous Pressurized Water Reactors (PWRs) and Fast Breeder Reactors (FBRs) using MOX/metallic fuel. The increase in the share of nuclear power through above technologies require setting up of fuel fabrication facilities such as: new PHWR Fuel Fabrication with indigenous sources, joint collaboration with foreign countries for fabricating fuel for imported LWRs, setting up PHWR fuel fabrication facilities with SEU/RU under international safeguards, setting up of enrichment and fuel fab rication facilities for indigenous PWRs and a series of fast reactor fuel fabrication facilities for fabricating fuel for FBRs. In addition to fuel fabrication facilities, facilities for manufacturing zirconium alloy and stainless steel structurals, tubes and components are also required to be set up. The paper gives in detail the emerging nuclear fuel fabrication activities in India. [Copyright &y& Elsevier]

Abstract: Materials play very crucial role for a safe, reliable and economic operation of nuclear power plants. Materials used in nuclear reactors encounter hostile environment and aggressive media during service, and are expected to retain their structural and metallurgical integrity over a long period of use. The major challenges are the effect of radiation on embrittlement, creep, erosion, corrosion, radiation induced growth, swelling, stress corrosion cracking, hydrogen embrittlement and radioactivity build up. In order to realize a high degree of reliabilit y and at the same time meet the imposing challenges, material specification and acceptance criteria are extremely stringent and the products have to undergo a detailed testing and characterization prior to their use. To ensure the conformance to the specification, processes need to be developed which involves melting the alloy with stringent chemistry control, optimizing thermo-mechanical treatment and modifying heat treatment schedule suitably to achieve mechanical properties. A typical nuclear power plant makes use of nuclear fuel materials such as uranium, structural materials such as zirconium alloys, stainless steels, nickel base alloys as well as low alloy and carbon steels. The paper outlines processing methodologies and gives an overview of some of the structural materials. [Copyright &y& Elsevier]

Abstract: A laboratory scale facility has been set up for fabrication of test fuel pins through sol-gel route for irradiation in FBTR, Kalpakkam. The facility is a train of glove boxes fitted with master slave manipulators for carrying out various operations involved in the fuel fabricat ion process. The paper describes the design features of the equipment and mechanisms for automation, developed for microsphere production and other processes. The design features include control system and vision systems for man- machine interface. [Copyright &y& Elsevier]

Abstract: The Fast Breeder Test Reactor at Kalpakkam has completed nearly 25 years of operation and is now operating at 18 MWt capacity with 46 fuel subassemblies (FSA) in the core consisting of 27 Mark-I (70% PuC+30% UC), 13 Mark-II (55% PuC+45% UC) and 6 MOX (44% PuO2+56% UO2) and one test PFBR FSA. Post Irradiation Examination (PIE) campaigns on FSAs at different burnup levels has provided valuable information about the irradiation behavior of the carbide fuel. This paper gives a summary of the irradiation performance of the carbide fuel evaluated through some of the investigations such as neutron radiography, X-Radiography, gamma scanning, fission gas analysis and ceramography. Burnup of the carbide fuel could be enhanced from the initial design burnup limit of 50 GWd/t to 165 GWd/ through systematic PIE. [Copyright &y& Elsevier]

Abstract: Shields around core and blankets form major part of reactor assembly in fast reactors. Among the advanced shield materials considered for use in future FBRs, planned to be constructed in India, Ferro-boron is a cheap and indigenously available material. This paper reports the results of experiments conducted in the south end neutron beam of KAMINI reactor on the fast, epithermal and thermal neutron flux attenuation behaviour of Ferro-boron with different percentages of boron as well as boron carbide. The attenuation factors were found over a thickness of 20-30cm for the measured reaction rates of Pt195 (n,n’) Pt195m, Cd111 (n, n’) Cd111m, Rh103(n,n’) Rh103, In115 (n,n’) In115m, Hf180(n,n’)Hf180m, Cu63 (n,) Cu64, Na23 (n,) Na24, Mn55 (n,) Mn56 and Au197 (n,) Au198 reactions representative of fast, epithermal and thermal neutron fluxes. A comparative analysis with the neutron attenuation behaviour measured in boron carbide powder is also made. [Copyright &y& Elsevier]

Abstract: Sodium cooled fast breeder reactors constitute the second stage of India''s three -stage nuclear energy programme, for effective utilization of the country''s limited reserves of natural uranium and exploitation of its large reserves of thorium. The Fast Breeder Test Reactor (FBTR) at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam, is a loop type, sodium cooled fast reactor. Its main aim is to provide experience in fast reactor operation, large scale sodium handling and to serve as a test bed for irradiation of fast reactor fuels & materials. FBTR was built on the lines of the French Rapsodie-Fortissimo reactor, with modifications to make it a generating plant. FBTR went critical on 18th Oct 1985 with a small core of 22 fuel subassemblies of a unique, high Pu carbide fuel. The core was rated for 10.5 MWt. The TG was rolled and synchronized to the grid in July 1997. Reactor power was progressively increased by enlarging the core, to reach 18.6 MWt. Several challenges in reactor operation came on the way, which were successfully overcome. A large number of modifications were carried out to improve the plant performance. The reactor coolant used (Sodium) is highly reactive when exposed to atmosphere and also becomes highly active on exposure to neutron radiation. These properties of sodium make it essential to handle it carefully and safely within a leak tight containment. During course of operation of the reactor, a number of sodium laden components viz. pumps, valves, cold traps, Rupture discs, level probes, shielding plugs, control rod drive mechanisms, experimental assemblies, piping etc. are required to be removed for various maintenance, modification and replacement jobs. This paper details the experience with operation and maintenance of India''s only one fast reactor power station. [Copyright &y& Elsevier]

Abstract: The BSC system of FBTR at Kalpakkam, India, is meant for maintaining the integrity of the concrete that surrounds the reactor vessel. Demineralized water is circulated through the BSC coils that are embedded in the concrete to maintain the concrete temperature below 800C. Water leak of 18 l/h from A3 sub loop of BSC system was first observed In Aug 2000. The chemical sealants required were developed at BARC and the methodology at IGCAR and using this, four leaking sub-loops of BSC system were sealed during 2007-2008 remotely. This paper details the salient features of this remote leak sealing technology. [Copyright &y& Elsevier]

Abstract: Charged particle accelerators were originally conceived and developed to explore the mysteries of atom in particular and to understand the structure of matter in general. Starting their journey since birth about 75 years ago, they have led to several discoveries, remarkable technological devolvement and useful applications in various walks of human life. Accelerators have evolved in various shapes and sizes, namely, electrostatic accelerators, linear accelerators, cyclotrons, synchrotrons, betatrons, storage rings, colliders etc. They have played fundamental role in our understanding about atom and nucleus, nuclear structure, sub-nuclear particles, fundamental forces, etc. In this paper role of accelerators in research and applications will be described with a particular emphasis on the accelerator programmes in India. [Copyright &y& Elsevier]

Abstract: The Prototype Fast Breeder Reactor (PFBR) is currently under construction at Kalpakkam, India. PFBR has eight numbers of sodium heated once through Steam Generators (SG) each with 157 MWt capacity. Parts like steam generator tube sheet will see high temperature gradients during normal operation as well as in transient conditions. Thermal baffles are provided to protect the steam generator tub e sheets from the high temperature gradients during transient and steady state conditions. In Steam Generator Test Facility (SGTF) of IGCAR a 5.5MWt capacity SG was tested for its thermal hydraulic performance. Effectiveness of the thermal baffles provided in the model SG of PFBR is studied numerically and the performance of the same has been predicted. Further Transient experiments were conducted in Steam Generator Test Facility for evaluating the same. This paper brings out the details of numerical studies and the experimental evaluation of the effectiveness of thermal baffles provided to protect the steam generator tube sheets. [Copyright &y& Elsevier]

Abstract: The total installed capacity of electric power generating in India is170288MW. The maximum demand during summer is 8000MW, during winter is 5500MW and during monsoon is 7000MW. The power generation is always less than the required demand. The power shortage varies from 2000MW to 4000MW. The gap between the generation and demand is to increase the generation capacity. But in developing country like India, it is not possible to install more capacity instantly. So the other important way to reduce the gap is energy conservation. In this paper it was proposed to implement energy conservation through energy efficiency and energy management. [Copyright &y& Elsevier]

Abstract: MicroSources and Renewable Energy sources refers to Distributed energy resources(DERs) and MicroGrids refers to a distribution network for electrical energy,starting from electricity generation to its transmission and storage with the ability to respond to dynamic changes on energy supply through co-generation and demand adjustment.Utilising potential of available distributed energy sources, MicroGrids can provide improved electric service reliability and better power quality to end users of electricity at conservative approach which might not be with the MicroGrids (centralized power grids). A worldwide research is going on MicroGrids, its application and control to overcome the weaknesses of the centralized power grids. In India due to power crisis a heavy load shedding has been carried out since last five years as load demand increasing day by day. Presently the concept of MicroGrids has been utilizing in rural areas of countries namely Canada, US, UK, Kenya etc. India is also having rich potential for Distributed energy resources (DERs). In this paper, potential of Distributed energy resources (DERs) in rural areas of Maharashtra state India has been predicted and suggested how application of Microgrids can reduce energy losses, improve power quality, deliver sustained power by Zero Load Shedding Model. [Copyright &y& Elsevier]

Abstract: India, which is in the mid latitude region, has extremly hot summers on its plains. In Northern and Central region of the country the maximum day temperature often goes beyond 45°C. The temperature inside the buildings, which generally have horizontal RCC roof, is unbearable without air conditioning. The steep rise in the cost of electricity has driven architects and builders to use passive cooling techniques in the construction. In this paper we examine the present methods that use an insulation layer to reduce the heat flux entering the living space bringing out their merits and demerits. Further we present an innovative approach in roof design that incorporates a layer of fly ash pieces which works as a porous insulation layer. The method has been implemented in a residential building in Delhi (28.380N). The experimental results demonstrate that the layer provides excellent insulation and it also shows structural stability. [Copyright &y& Elsevier]