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Fundamental approaches for analysis thermal hydraulic parameter for Puspati Research Reactor
Author(s) -
Zaredah Hashim,
Tonny Anak Lanyau,
Mohamad Fairus Abdul Farid,
Mohammad Suhaimi Kassim,
Noraishah Syahirah Azhar
Publication year - 2016
Publication title -
aip conference proceedings
Language(s) - Uncategorized
Resource type - Conference proceedings
eISSN - 1551-7616
pISSN - 0094-243X
DOI - 10.1063/1.4940064
Subject(s) - triga , thermal hydraulics , nuclear engineering , research reactor , coolant , cladding (metalworking) , nuclear reactor core , control rod , nuclear reactor , environmental science , physics , materials science , mechanics , nuclear physics , heat transfer , engineering , neutron , metallurgy

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