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3 articles for “FBTR”
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Wireless Sensor Network in Fast Breeder Test Reactor
Abstract: The second stage of India’s three-stage nuclear energy programme envisages of the development of Sodium cooled fast breeder reactors. As a forerunner, Fast Breeder Test Reactor (FBTR) at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam has been constructed. It is being operated successfully for more than 27 years. FBTR provides experience in fast reactor operation, fuel behavior, large scale sodium handling and is serving as a test bed for …
Published in Journal of Nuclear Engineering & Technology · Vol. 3, Issue 1, 2013 Read article
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Challenges In Sodium Cooled Fast Reactor Thermal Hydraulics
Abstract: Heat Transfer and Fluid flow phenomena (referred as Thermal Hydraulics) play a significant role in the safe and economical design of fast breeder reactors (FBR). The sodium cooled fast reactors have a very complex flow and temperature profile within the pool or the test vessel. The high temperature operating conditions (~540 deg.C) also impose stringent requirements on the thermal design of the components. The basic approach of thermal hydraulic design …
Published in Journal of Nuclear Engineering & Technology · Vol. 12, Issue 2, 2022 · pp. 33–47 Read article
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Execution of a Large Engineering Project in an R&D Institution- Some Experiences
Abstract: Steam Generator Test Facility (SGTF) was set up mainly to validate the design of the steam generator of the Prototype Fast Breeder Reactor (PFBR). PFBR is a power reactor of 500 MWe after the successful Fast Breeder Test Reactor (FBTR). FBTR was built in collaboration with French Atomic Energy Commission (CEA). It was similar to the 40 MWt Rapsodie reactor but had SG modules of the Phenix reactor design in …
Published in Journal of Nuclear Engineering & Technology · Vol. 12, Issue 3, 2022 · pp. 27–35 Read article