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...
Furkejuvvon:
| Váldodahkkit: | , , , , |
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| Materiálatiipa: | Artigo |
| Giella: | Inglês |
| Almmustuhtton: |
Universitas Indonesia
2017-07-01
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| Ráidu: | International Journal of Technology |
| Fáttát: | |
| Liŋkkat: | http://ijtech.eng.ui.ac.id/article/view/578 |
| Fáddágilkorat: |
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