Search Results - "Suresh Kumar, V.A."
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Investigation into steam generator tube life expectancy affected by SFR transients
Published in Progress in nuclear energy (New series) (01-01-2022)“…One of the decay heat removal systems in sodium cooled fast reactors (SFR) is the operation grade decay heat removal system (OGDHRS). During deployment of…”
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Failure analysis of a reducer section in the creep loop of INSOT facility
Published in Engineering failure analysis (01-02-2023)“…•Sodium leak was observed in a reducer component of the INSOT (in-sodium testing) facility.•The reducer component was fabricated out of Ni based Alloy…”
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Experimental evaluation of the heat transfer performance of sodium heated once through steam generator
Published in Nuclear engineering and design (01-07-2014)“…•PFBR has eight units of steam generators to transfer 1250MWt power.•A model steam generator was tested for its heat transfer performance.•The model steam…”
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Experimental evaluation of sodium to air heat exchanger performance
Published in Annals of nuclear energy (01-08-2013)“…► Sodium to air heat exchangers are used to remove the decay heat produced in fast breeder reactor after shutdown. ► Finned tube sodium to air heat exchanger…”
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In-situ calibration of permanent magnet flow meters in PFBR using noise analysis technique
Published in Flow measurement and instrumentation (01-12-2013)“…In Fast Breeder Reactor sodium circuits, permanent magnet flow meters (PMFM) are extensively used to measure the liquid sodium flow rate. The performance of…”
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Steam generator test facility—A test bed for steam generators of Indian sodium cooled fast breeder reactors
Published in Nuclear engineering and design (01-07-2012)“…► Performance testing of a 5.5MW capacity once through straight tube steam generator. ► 5000h of endurance test has demonstrated the steam generator design. ►…”
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