Ditemukan 2 dokumen yang sesuai dengan query
Anhar Riza Antariksawan, author
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...
Depok: Faculty of Engineering, Universitas Indonesia, 2017
UI-IJTECH 8:4 (2017)
Artikel Jurnal Universitas Indonesia Library
Muhammad Darwis Isnaini, author
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...
Pusat Teknologi Reaktor dan keselamatan nuklir, BATAN, 2016
620 JTRN 18:1 (2016)
Artikel Jurnal Universitas Indonesia Library
