The Experts below are selected from a list of 117 Experts worldwide ranked by ideXlab platform
S Varatharajan - One of the best experts on this subject based on the ideXlab platform.
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development of fast Breeder Reactor technology in india
Progress in Nuclear Energy, 2017Co-Authors: P. Puthiyavinayagam, K Velusamy, V. Balasubramaniyan, S. Raghupathy, P Selvaraj, K Devan, B K Nashine, Padma G Kumar, K Suresh V Kumar, S VaratharajanAbstract:Abstract India is pursuing a three stage nuclear power program employing its natural uranium and Thorium reserves. FBRs form the second stage of the program linking the first phase with natural U and third phase with Th fuels. The saga of FBR technology development in India is presented in this paper. The valuable experience in design and operation of Fast Breeder Test Reactor (FBTR) is recounted briefly. The R&D for the techno-economic demonstration of Prototype Fast Breeder Reactor (PFBR) is explained including technology development for addressing manufacturing challenges and engineering full-scale qualification. Finally a brief projection is made on the developments for FBR600 with improved safety and economics as well as metal fuel technology for future experimental and power Reactors to follow.
P. Puthiyavinayagam - One of the best experts on this subject based on the ideXlab platform.
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development of fast Breeder Reactor technology in india
Progress in Nuclear Energy, 2017Co-Authors: P. Puthiyavinayagam, K Velusamy, V. Balasubramaniyan, S. Raghupathy, P Selvaraj, K Devan, B K Nashine, Padma G Kumar, K Suresh V Kumar, S VaratharajanAbstract:Abstract India is pursuing a three stage nuclear power program employing its natural uranium and Thorium reserves. FBRs form the second stage of the program linking the first phase with natural U and third phase with Th fuels. The saga of FBR technology development in India is presented in this paper. The valuable experience in design and operation of Fast Breeder Test Reactor (FBTR) is recounted briefly. The R&D for the techno-economic demonstration of Prototype Fast Breeder Reactor (PFBR) is explained including technology development for addressing manufacturing challenges and engineering full-scale qualification. Finally a brief projection is made on the developments for FBR600 with improved safety and economics as well as metal fuel technology for future experimental and power Reactors to follow.
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The design of the prototype Fast Breeder Reactor
Nuclear Engineering and Design, 2006Co-Authors: S C Chetal, P Chellapandi, V. Balasubramaniyan, P. Mohanakrishnan, P. Puthiyavinayagam, C.p. Pillai, S. Raghupathy, T.k. Shanmugham, C. Sivathanu PillaiAbstract:India has a moderate uranium reserve and a large thorium reserve. The primary energy resource for electricity generation in the country is coal. The potential of other resources like gas, oil, wind, solar and biomass is very limited. The only viable and sustainable resource is the nuclear energy. Presently, Pressurised Heavy Water Reactors utilizing natural uranium are in operation/under construction and the plutonium generated from these Reactors will be multiplied through breeding in fast Breeder Reactors. The successful construction, commissioning and operation of Fast Breeder Test Reactor at Kalpakkam has given confidence to embark on the construction of the Prototype Fast Breeder Reactor (PFBR). This paper describes the salient design features of PFBR including the design of the Reactor core, Reactor assembly, main heat transport systems, component handling, steam water system, electrical power systems, instrumentation and control, plant layout, safety and research and development.
D.b. Illum - One of the best experts on this subject based on the ideXlab platform.
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Fuel Summary Report: Shippingport Light Water Breeder Reactor - Rev. 2
2002Co-Authors: G.l. Olson, Richard Keith Mc Cardell, D.b. IllumAbstract:The Shippingport Light Water Breeder Reactor (LWBR) was developed by Bettis Atomic Power Laboratory to demonstrate the potential of a water-cooled, thorium oxide fuel cycle Breeder Reactor. The LWBR core operated from 1977-82 without major incident. The fuel and fuel components suffered minimal damage during operation, and the Reactor testing was deemed successful. Extensive destructive and nondestructive postirradiation examinations confirmed that the fuel was in good condition with minimal amounts of cladding deformities and fuel pellet cracks. Fuel was placed in wet storage upon arrival at the Expended Core Facility, then dried and sent to the Idaho Nuclear Technology and Engineering Center for underground dry storage. It is likely that the fuel remains in good condition at its current underground dry storage location at the Idaho Nuclear Technology and Engineering Center. Reports show no indication of damage to the core associated with shipping, loading, or storage
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Fuel Summary Report: Shippingport Light Water Breeder Reactor
1999Co-Authors: D.b. Illum, G.l. Olson, R.k. MccardellAbstract:The Shippingport Light Water Breeder Reactor (LWBR) was developed by Bettis Atomic Power Laboratory to demonstrate the potential of a water-cooled, thorium oxide fuel cycle Breeder Reactor. The LWBR core operated from 1977-82 without major incident. The fuel and fuel components suffered minimal damage during operation, and the Reactor testing was deemed successful. Extensive destructive and nondestructive postirradiation examinations confirmed that the fuel was in good condition with minimal amounts of cladding deformities and fuel pellet cracks. Fuel was placed in wet storage upon arrival at the Expended Core Facility, then dried and sent to the Idaho Nuclear Technology and Engineering Center for underground dry storage. It is likely that the fuel remains in good condition at its current underground dry storage location at the Idaho Nuclear Technology and Engineering Center. Reports show no indication of damage to the core associated with shipping, loading, or storage.
Usha Pal - One of the best experts on this subject based on the ideXlab platform.
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A Comparison of Fast Thorium Breeder Reactor Designs With Oxide and Metallic Fuels
Volume 1: Plant Operations Maintenance Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Tech, 2008Co-Authors: V. Jagannathan, Usha Pal, R. Karthikeyan, Devesh RajAbstract:Loading of seedless thoria rods in internal blanket regions and using them later as part of seeded fuel assemblies is the central theme of the thorium Breeder Reactor (ATBR) concept [1]. The fast Reactors presently consider seedless blanket region surrounding the seeded core region. This results in slower fissile production rate in comparison to fissile depletion rate per unit volume. The overall breeding is achieved mainly by employing blanket core with more than double the volume of seeded core. The blanket fuel is discharged with fissile content of ∼30g/kg, which is much less than the asymptotic maximum possible fissile content of 100g/kg. This is due to smaller coolant flow provided for in the blanket regions. In a newly proposed fast thorium Breeder Reactor (FTBR) [2], the blanket region is brought in and distributed through out the core. By this the fissile depletion and production rates per unit volume become comparable. The core considered simultaneous breeding from both fertile thoria and depleted uranium and hence the concept can be called as fast twin Breeder Reactor as well. Sodium is used as coolant. The blanket fuel rods achieve nearly 80% of the seed fuel rod burnup and also contain nearly the maximum possible fissile content at the time of discharge. In this paper a comparison of FTBR core characteristics with oxide and metallic fuel are compared.
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towards an intrinsically safe and economic thorium Breeder Reactor
Energy Conversion and Management, 2006Co-Authors: V. Jagannathan, Usha PalAbstract:Abstract Thorium does not have intrinsic fissile content unlike uranium. 232Th has nearly three times thermal absorption cross section compared to 238U and hence requires much larger externally fed fissile content compared to uranium based fuel. These factors give a permanent economic competitive edge to uranium. Thus thorium is not inducted in any significant measure in present day power Reactors, despite the fact that thorium is three times more abundant in the earth’s crust than uranium. Uranium reserves vary from country to country and there is also difficulty in having equitable distribution of uranium. Thus when 235U would get exhausted, perhaps much sooner in countries having limited uranium reserve, there will be a need to switch over from the today’s open fuel cycle programme based on 235U feed to closed fuel cycle based on Pu feed. At that stage thorium and (depleted) uranium would become equal candidates to form the fertile base. All economic considerations would have to be readdressed. The size and growth of the nuclear power programme based on closed fuel cycle would be dependent on maximizing the fissile conversion rate in those Reactors. In this paper we reemphasize the principles and the details of the thermal Reactor concept ‘A Thorium Breeder Reactor’ (ATBR), in which the use of PuO2 seeded thoria fuel is found to give excellent core characteristics like two years cycle length with nearly zero control maneuvers, fairly high seed output to input ratio and intrinsically safe reactivity coefficients [Jagannathan V, Ganesan S, Karthikeyan R. Sensitivity studies for a thorium Breeder Reactor design with the nuclear data libraries of WIMS library update project. In: Proceedings of the international conference on emerging nuclear energy systems ICENES-2000, September 25–28, 2000, Petten, The Netherlands].
Matthew Hannon - One of the best experts on this subject based on the ideXlab platform.
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Fast Breeder Reactor technology and the entrepreneurial state in the UK
Business History, 2020Co-Authors: Niall Mackenzie, Stephen Knox, Matthew HannonAbstract:This article explores the creation, operation and failure of the UK’s fast Breeder Reactor programme at Dounreay within the context of the development of the nuclear power industry in the UK, and t...