Relevant bibliographies by topics / Prototype Fast Breeder Reactor (PFBR)

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  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Prototype Fast Breeder Reactor (PFBR)'

Author: Grafiati
Published: 4 June 2021
Last updated: 25 July 2025

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Journal articles on the topic "Prototype Fast Breeder Reactor (PFBR)"

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Anuraj, Vijayan, Goverapet Srinivasan, and Kunhiraman Devan. "Stability characteristics of the 500 mw Indian PFBR." Nuclear Technology and Radiation Protection 30, no. 2 (2015): 113–23. http://dx.doi.org/10.2298/ntrp1502113a.

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After the successful operation of the fast breeder test reactor for over two decades, India is now nearing the completion of a 500 MW (electrical) prototype fast breeder reactor. This commercial scale power reactor is a sodium-cooled, pool-type, mixed-oxide fuelled fast reactor. The stability characteristics of the reactor are an important safety aspect to be studied. In the present work, linear stability of the prototype fast breeder reactor analysis is carried out using the transfer function method, while the stability of the system is checked via the Nyquist criteria. For the completeness o
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Kumar, Prabhat. "Welding and Fabrication of Stainless Steel Equipment for 500MWe Prototype Fast Breeder Reactor." Advanced Materials Research 794 (September 2013): 305–15. http://dx.doi.org/10.4028/www.scientific.net/amr.794.305.

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Austenitic stainless steel is the major structural material for the primary and secondary sodium systems (except for the steam generators) for the currently operating and planned fast reactors all over the world. The boundaries of sodium systems of Prototype Fast Breeder Reactor (PFBR) is designed so as to have an extremely low probability of leakage, rapidly propagating failure and gross rupture under the static & dynamic loads expected during various operating conditions.The degradation of material properties (e.g. effect of sodium, temperature and irradiation), transients, residual stre
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Azhagarason, B., N. Mahendran, Tarun Kumar Mitra, and Prabhat Kumar. "Technological Challenges in Manufacturing of over Dimensional Stainless Steel Components of PFBR." Advanced Materials Research 794 (September 2013): 186–93. http://dx.doi.org/10.4028/www.scientific.net/amr.794.186.

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Prototype Fast Breeder Reactor (PFBR) is liquid sodium cooled, pool type nuclear reactor with generating capacity of 1250 MWt / 500MWe. Reactor assembly consists of many large dimensional components made of special grade austenitic stainless steel material. Safety vessel and Main vessel are torispherical dished end vessels with overall height of 12.8 m and 13.4/12.9 m diameter with thickness ranging from 20 to 40 mm. Vessels approx. 111 / 135 MT with running weld length of 500 & 540 m. Inner vessel and thermal baffles are the internals of reactor assembly made of SS 316LN. Forming of dishe
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Balaguru, S., K. Deenadayalan, Murali Vela, and P. Chellapandi. "Influence of Welding Speed over Dilution for Circular Grid Plate Hardfaced with Colmonoy-5." Applied Mechanics and Materials 565 (June 2014): 53–58. http://dx.doi.org/10.4028/www.scientific.net/amm.565.53.

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Colmonoy is a nickel based alloy hardfaced with SS-316 used in Prototype Fast Breeder Reactors (PFBR) to avoid self-welding and galling between nuclear reactor and grid plate. Colmonoy is coated on the base metal –SS 316 by Plasma transfer arc welding. Due to thermal cycling that exist in reactors de-bonding between colmonoy and base metal occurs which may lead to catastrophic failure of the Prototype fast breeder reactor. Hence, estimation of the fatigue life period of hardfaced colmonoy is mandatory. Before that, finding optimum parameters which influences fusion, weld strength, composition
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Dutta, N. G. "Helium Leak Detection of Vessels in Fuel Transfer Cell (FTC) of Prototype Fast Breeder Reactor (PFBR)." Journal of Physics: Conference Series 390 (November 5, 2012): 012080. http://dx.doi.org/10.1088/1742-6596/390/1/012080.

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Balaguru, S., K. Saranraj, Murali Vela, and P. Chellapandi. "Variation in Residual Stresses due to Thermal Cycling Induced on the Hardfaced Grid Plate in PFBR." Applied Mechanics and Materials 591 (July 2014): 98–102. http://dx.doi.org/10.4028/www.scientific.net/amm.591.98.

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In sodium cooled fast breeder reactors, the high operating temperature necessitates hard facing of grid plate to avoid galling and to reduce the wear loss of the base material . Nickel-base cobalt-free alloy called Colmonoy-5 has been chosen as the hard facing material for the Prototype Fast Breeder Reactor (PFBR) grid plate. The grid plate (GP) which is a critical component made of 316 LN SS that holds the core subassemblies are hard faced, to prevent galling and also to minimize wear caused by subassembly insertion/removal and erosion due to high sodium velocity at 670 K. Thermal cycling of
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Rangasamy, R. G., and Prabhat Kumar. "Quality Management during Manufacturing of High Tempertaure Thin Walled Austenitic Stainless Steel Sodium Tanks of Prototype Fast Breeder Reactor." Advanced Materials Research 794 (September 2013): 507–13. http://dx.doi.org/10.4028/www.scientific.net/amr.794.507.

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Austenitic stainless steels are the major material of construction for the fast breeder reactors in view of their adequate high temperature mechanical properties, compatibility with liquid sodium coolant, good weldability, availability of design data and above all the fairly vast and satisfactory experience in the use of these steels for high temperature service. All the Nuclear Steam Supply System (NSSS) components of FBR are thin walled structure and require manufacture to very close tolerances under nuclear clean conditions. As a result of high temperature operation and thin wall constructi
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Sankar, Bindu, K. Vijaya kumar, j. Rajan, and s. Rajeswari. "DESIGN AND DEVELOPMENT OF HMI IN SIMULATOR FOR FRESH FUEL HANDLING SYSTEM." International Journal of Engineering Applied Sciences and Technology 8, no. 1 (2023): 162–68. http://dx.doi.org/10.33564/ijeast.2023.v08i01.030.

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KALBRSIM operator training simulator is used for training Prototype Fast Breeder Reactor (PFBR) nuclear power plant operators. In simulator, using virtual panel HMI which is an exact replica of actual hardware panels, all the essential fresh fuel operations can be done. Visualization power is also provided by 3D models which aid in quicker understanding of the complex process involved in Fresh Fuel Handling System (FFHS). Operation using Virtual Panel is an excellent tool for system developers to test the logic and process models of FFHS in KALBRSIM before integration with hardware panels. Als
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Perumalsamy, G., P. Visweswaran, D. Jagadishan, S. Joseph Winston, and S. Murugan. "Optimisation of helical geometry of inspection probe for steam generator tubes of the PFBR." Insight - Non-Destructive Testing and Condition Monitoring 63, no. 10 (2021): 585–91. http://dx.doi.org/10.1784/insi.2021.63.10.585.

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The steam generator (SG) tubes of the prototype fast breeder reactor (PFBR) located in Kalpakkam, India, need to be periodically inspected using the remote field eddy current (RFEC) technique. During the pre-service inspection of the SG tubes, it was found that the RFEC probes experienced frequent mechanical breakages. To avoid these failures, changes in the existing structural design of the RFEC probe were required. A helical groove design was proposed to obtain a smooth transition in the variation of stress across the probe during the inspection. It was difficult to calculate the flexural st
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Balaguru, S., K. Saranraj, Murali Vela, and P. Chellapandi. "Evaluation of Stress Intensity Factor of 316 SS LN Circular Grid Plate Hardfaced with Colmonoy 5 for Various Loads." Applied Mechanics and Materials 431 (October 2013): 173–76. http://dx.doi.org/10.4028/www.scientific.net/amm.431.173.

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In sodium cooled fast breeder reactors, the high operating temperature necessitates hardfacing of grid plate to avoid galling of the base material. Nickel based cobalt-free alloy called Colmonoy-5 has been chosen as the hard facing material for the Prototype Fast Breeder Reactor (PFBR) grid plate. The grid plate (GP) which is a critical component made of SS316 that holds the core subassemblies are hard faced, to prevent galling caused by subassembly insertion/removal and erosion due to high sodium velocity at 670 K. Colmonoy 5 was hardfaced on circular grid plate along the annular groove by Pl
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Dissertations / Theses on the topic "Prototype Fast Breeder Reactor (PFBR)"

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Sajish, S. D. "Reliability And Response Uncertainty Analyses Of Piping And Shutdown Systems Of Nuclear Power Plants Under Seismic Loading." Thesis, 2011. https://etd.iisc.ac.in/handle/2005/1989.

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Earthquake safety engineering of nuclear power plant structures poses several challenges to the analyst and designer. These problems are characterized by highly transient and dynamic nature of earthquake induced excitations, random nature of details of support motions (in terms of duration, frequency content, amplitude modulation, multiple components, and spatial variability), nonlinear nature of structural behavior, geometrical complexity of the primary and a large number of secondary systems (such as, for example, piping, rotors, and machine panels), soil-structure interactions, demands on h
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Sajish, S. D. "Reliability And Response Uncertainty Analyses Of Piping And Shutdown Systems Of Nuclear Power Plants Under Seismic Loading." Thesis, 2011. http://etd.iisc.ernet.in/handle/2005/1989.

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Earthquake safety engineering of nuclear power plant structures poses several challenges to the analyst and designer. These problems are characterized by highly transient and dynamic nature of earthquake induced excitations, random nature of details of support motions (in terms of duration, frequency content, amplitude modulation, multiple components, and spatial variability), nonlinear nature of structural behavior, geometrical complexity of the primary and a large number of secondary systems (such as, for example, piping, rotors, and machine panels), soil-structure interactions, demands on h
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Books on the topic "Prototype Fast Breeder Reactor (PFBR)"

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Srivastava, A. P., of Research Reactor Services Division, Bhabha Atomic Research Centre. and Bhabha Atomic Research Centre, eds. Engineering design and development for prototype fast breeder reactor (PFBR) shielding experiments at APSARA. Bhabha Atomic Research Centre, 2003.

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V, Suresh Varma P., and Bhabha Atomic Research Centre, eds. Pulsed Nd-YAG laser welding of prototype fast breeder reactor fuel elements. Bhabha Atomic Research Centre, 2009.

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V, Suresh Varma P., and Bhabha Atomic Research Centre, eds. Pulsed Nd-YAG laser welding of prototype fast breeder reactor fuel elements: [BARC report]. Bhabha Atomic Research Centre, 2009.

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Pulsed Nd-YAG laser welding of prototype fast breeder reactor fuel elements. Bhabha Atomic Research Centre, 2009.

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Pulsed Nd-YAG laser welding of prototype fast breeder reactor fuel elements. Bhabha Atomic Research Centre, 2009.

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Book chapters on the topic "Prototype Fast Breeder Reactor (PFBR)"

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Joseph Winston, S., S. Sakthivel, Joel Jose, et al. "Prototype Fast Breeder Reactor Steam Generator Inspection System for Tube Inspections." In Lecture Notes in Mechanical Engineering. Springer Singapore, 2018. http://dx.doi.org/10.1007/978-981-10-8597-0_61.

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Bachchan, Abhitab, K. Devan, G. Pandikumar, and P. Puthiyavinayagam. "Evolution of Actinides in ThO2 Radial Blanket of Prototype Fast Breeder Reactor." In Thorium—Energy for the Future. Springer Singapore, 2019. http://dx.doi.org/10.1007/978-981-13-2658-5_11.

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Winston, S. Joseph, Joel Jose, Arun Subramaniyan, S. Murugan, and A. K. Bhaduri. "Rigid Body Transformations for Calibration of Prototype Fast Breeder Reactor, Steam Generator Inspection Device." In Communications in Computer and Information Science. Springer Singapore, 2016. http://dx.doi.org/10.1007/978-981-10-2845-8_3.

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Chithira, P., N. Kanagalakshmi, P. Rajavelu, R. Prasanna, P. Sreenivasa Rao, and V. Magesh Mari Raj. "Risk-Based Approach for Thermal Profiling of Sodium Vessel and Pipelines of Prototype Fast Breeder Reactor." In Reliability, Safety and Hazard Assessment for Risk-Based Technologies. Springer Singapore, 2019. http://dx.doi.org/10.1007/978-981-13-9008-1_82.

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Joseph Winston, S., Joel Jose, D. Jagadishan, et al. "Degenerated Degree of Freedom Sensing Without Loss of Accuracy While Estimating the Rigid Body Parameters for the Calibration of a Two-Axis Robotic Arm for Prototype Fast Breeder Reactor, Steam Generator Inspection System." In Lecture Notes in Mechanical Engineering. Springer Singapore, 2018. http://dx.doi.org/10.1007/978-981-10-8597-0_53.

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Conference papers on the topic "Prototype Fast Breeder Reactor (PFBR)"

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Vijayakumar, V., S. C. Chetal, K. Madhusoodanan, C. Paramasivan Pillai, M. Sakthivel, and Uma Seshadri. "Sodium and Steam Generator Leak Detection for Prototype Fast Breeder Reactor (PFBR)." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49362.

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Construction of Prototype Fast Breeder Reactor (PFBR) a 500 MWe pool type sodium cooled breeder reactor with MOX fuel has started at Kalpakkam. Instrumentation & Control (I&C) of PFBR is designed for safe, reliable and economic operation of the plant. Special feature of breeder reactors is sodium instrumentation. Leaks in sodium systems have the possibility of being exceptionally hazardous due to the reaction of liquid sodium with oxygen and water vapour in the air. In addition, leakage from primary systems can cause radioactive contamination. Potential regions of leakage are near weld
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Raju, Vijayashree, Rajan Babu Vinayagamoorthy, Parthasarathy Uppala, Sureshkumar Ramachandran, Raghupathy Sundararajan, and Chellapandi Perumal. "Design and Development of Failed Fuel Location Module for Prototype Fast Breeder Reactor." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30913.

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Prototype Fast Breeder Reactor (PFBR), India’s first commercial fast breeder reactor employing fast fission is a challenging project from technological point of view to meet the energy security of the country. PFBR is a sodium cooled fast reactor. There are 198 fuel sub assemblies with mixed oxide fuel in the reactor. The fuel is provided with a leak tight metal cladding for containment of the fission products. There are risks of sodium circuit contamination and the fission products blocking the coolant flow to the fuel sub assemblies in case of clad rupture and release of solid fission produc
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Vijayakumaran, P. M., C. P. Nagaraj, C. Paramasivan Pillai, R. Ramakrishnan, and M. Sivaramakrishna. "Nuclear Instrumentation Systems in Prototype Fast Breeder Reactor." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49354.

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The nuclear instrumentation systems of the Prototype Fast Breeder Reactor (PFBR) primarily comprise of global Neutron Flux Monitoring, Failed Fuel Detection & Location, Radiation Monitoring and Post-Accident Monitoring. High temperature fission chambers are provided at in-vessel locations for monitoring neutron flux. Failed fuel detection and location is by monitoring the cover gas for fission gases and primary sodium for delayed neutrons. Signals of the core monitoring detectors are used to initiate SCRAM to protect the reactor from various postulated initiating events. Radiation levels i
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Perumal, Chellapandi, V. Balasubramaniyan, P. Puthiyavinayagam, et al. "Design of 500 MWe Metal Fuel Demonstration Fast Reactor." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30727.

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Indian nuclear power programme is being implemented in three stages taking in to consideration limited uranium resources and vast thorium resources in the country. The first stage consists of investing natural uranium in Pressurized Heavy Water Reactors (PHWR). This stage has the potential of 10 GWe. The second stage involves large scale deployment of Fast Breeder Reactors (FBR) with co-located fuel cycle facilities to utilize the plutonium and depleted uranium extracted from the PHWR spent fuel. This stage has a potential of about 300 GWe. In the third stage, effective utilization of the vast
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Rajan, K. K., G. Vijayakumar, S. Chandramouli, K. Madhusoodhanan, P. Kalyanasundaram, and G. Vaidyanathan. "Experimental Evaluation of Wire Type Leak Detector Layout for Prototype Fast Breeder Reactor (PFBR)." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75822.

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Wire type leak detectors working on conductivity principle are used for detecting sodium leak in the secondary sodium circuits of FBRs. It is required to assess the performance of these detectors and confirm that they are meeting the requirements. A test facility by name LEENA was constructed at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam to test the wire type leak detector lay out by simulating sodium leaks of different rates. This test facility consists of a sodium dump tank, a test vessel, interconnecting pipelines with valves, micro filter and test section with leak simulat
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Vijayashree, R., P. ChellaPandi, K. Natesan, S. Jalaldeen, S. C. Chetal, and Baldev Raj. "Design and Development of Diverse Safety Rod and Its Drive Mechanism for PFBR." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75851.

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Prototype Fast Breeder Reactor (PFBR) is U-PuO2 fuelled sodium cooled Pool type Fast Reactor and it is currently under advanced stage of construction at Kalpakkam, India. The Fast Breeder Test Reactor (FBTR) which is the only fast reactor currently operational in India is having only one shutdown system. However the IAEA and Atomic Energy Regulatory Board (AERB) Guide Lines call for two independent fast acting diverse shutdown systems for the present generation reactors. Hence PFBR is equipped with two independent, fast acting and diverse shutdown systems. A shutdown system comprises of sensor
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Babu V., Rajan, V. Balasubramaniyan, Raghupathy Sundararajan, P. Puthiyavinayagam, and Chellapandi Perumal. "Design Improvement Studies for Future SFR." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30742.

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Prototype Fast Breeder Reactor (PFBR), a 500 MWe, (U-Pu)O2 fuelled, sodium cooled, pool type fast reactor, is in advanced stage of construction at Kalpakkam, India. Based on the experience gained during the design, manufacture and erection of various reactor components of PFBR, it is planned to construct Sodium cooled Fast Reactors (SFR) by adopting twin unit (2×500 MWe reactors) concept. The future Fast Breeder Reactor (FBR) – 1 & 2 have three main heat transport circuits, namely primary sodium, secondary sodium and steam-water systems. All the reactor internals including core and primary
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Rao, P. M., N. Kasinathan, and S. E. Kannan. "Analysis of Sodium Fire in the Containment Building of Prototype Fast Breeder Reactor Under the Scenario of Core Disruptive Accident." In 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89566.

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The potential for sodium release to reactor containment building from reactor assembly during Core Disruptive Accident (CDA) in Fast Breeder Reactors (FBR) is an important safety issue with reference to the structural integrity of Reactor Containment Building (RCB). For Prototype Fast Breeder Reactor (PFBR), the estimated sodium release under a CDA of 100 MJ energy release is 350 kg. The ejected sodium reacts easily with air in RCB and causes temperature and pressure rise in the RCB. For estimating the severe thermal consequences in RCB, different modes of sodium fires like pool and spray fire
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Joseph, Jofred, Satish Kumar, Tanmay Vasal, and N. Theivarajan. "Brayton Cycle As an Alternate Power Conversion Option for Sodium Cooled Fast Reactor." In ASME 2019 Gas Turbine India Conference. American Society of Mechanical Engineers, 2019. http://dx.doi.org/10.1115/gtindia2019-2455.

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Abstract Enhancing the safety and economic competitiveness are major objectives in the development of advanced reactor designs with emphasis on the design of systems or components of the nuclear systems. Innovative power cycle development is another potential option to achieve these objectives. Sodium cooled fast reactor (SFR) is one among the six reactor design concepts identified by the Gen IV International Forum for development to meet the technology goals for new nuclear energy system. Similar to the power cycle used in conventional fossil fuel based thermal power plants, sodium-cooled fas
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Prakash, V., M. Anandaraj, M. Thirumalai, P. Kalyanasundaram, and G. Vaidyanathan. "Application of Acoustic Technique for Surveillance and Anomaly Detection in LMFBRs." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48252.

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Acoustic techniques find wide application in Liquid Metal Fast Breeder Reactors (LMFBRs) for ensuring its high reliability, safety and plant availability. Various surveillance methods based on acoustic technique can be employed in these reactors to detect deviations from normal operating conditions. This could be used for the measurement of drop time of Diverse Safety Rods (DSRs) in the core, detection of in-sodium water leaks in Steam Generators, cavitation detection in sodium pumps and reactor core components. An active R&D program is being pursued in these areas at Indira Gandhi Centre
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Reports on the topic "Prototype Fast Breeder Reactor (PFBR)"

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Velusamy, K., V. Balaubramanian, G. Vaidyanathan, and S. C. Chetal. Conjugate heat transfer analysis of multiple enclosures in prototype fast breeder reactor. Office of Scientific and Technical Information (OSTI), 1995. http://dx.doi.org/10.2172/107784.

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