Ditemukan 2 dokumen yang sesuai dengan query
Anhar Riza Antariksawan
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Any events presumed to risk the safety of a nuclear reactor should be analyzed. In a research reactor, the applicability of best estimate thermal-hydraulic codes has been assessed for safety analysis purposes. In this paper, the applicability of the RELAP/SCDAPSIM/MOD3.4 thermal-hydraulic code to one Indonesian research reactor, which is named TRIGA-2000, is performed. The aim is to validate the model and use the model to analyze the thermal-hydraulic characteristics of TRIGA-2000 for main transient events ...
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Depok: Faculty of Engineering, Universitas Indonesia, 2017
UI-IJTECH 8:4 (2017)
Artikel Jurnal Universitas Indonesia Library
Muhammad Darwis Isnaini
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The validation of Pressurized Water Reactor typed Nuclear Power Plant simulator developed by BATAN (SIMBAT-PWR) using standard code of COBRA-EN on reactor transient condition has been done. The development of SIMBAT-PWR has accomplished several neutronics and thermal-hydraulic calculation modules. Therefore, the validation of the simulator is needed, especially in transient reactor operation condition. The research purpose is for characterizing the thermal-hydraulic parameters of PWR1000 core, which is able to be applied or as a comparison ...
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Pusat Teknologi Reaktor dan keselamatan nuklir, BATAN, 2016
620 JTRN 18:1 (2016)
Artikel Jurnal Universitas Indonesia Library
