TRIGA-2000 Research Reactor Thermal-hydraulic Analysis using RELAP/SCDAPSIM/MOD3.4

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 on...

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מידע ביבליוגרפי

Principais autores:	Anhar Riza Antariksawan, Efrizon Umar, Surip Widodo, Mulya Juarsa, Mukhsinun Hadi Kusuma
פורמט:	Artigo
שפה:	Inglês
יצא לאור:	Universitas Indonesia 2017-07-01
סדרה:	International Journal of Technology
נושאים:	Loss of coolant Loss of flow RELAP5 Research reactor TRIGA
גישה מקוונת:	http://ijtech.eng.ui.ac.id/article/view/578
תגים:	הוספת תג אין תגיות, היה/י הראשונ/ה לתייג את הרשומה!