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Surip Widodo
Surip Widodo
BRIN
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Zitiert von
Zitiert von
Jahr
Passive cooling system in a nuclear spent fuel pool using a vertical straight wickless-heat pipe
MH Kusuma, N Putra, AR Antariksawan, RA Koestoer, S Widodo, ...
International Journal of Thermal Sciences 126, 162-171, 2018
622018
Fuzzy probability based event tree analysis for calculating core damage frequency in nuclear power plant probabilistic safety assessment
JH Purba, DTS Tjahyani, S Widodo, AS Ekariansyah
Progress in Nuclear Energy 125, 103376, 2020
282020
α-Cut method based importance measure for criticality analysis in fuzzy probability–Based fault tree analysis
JH Purba, DTS Tjahyani, S Widodo, H Tjahjono
Annals of Nuclear Energy 110, 234-243, 2017
272017
Simulation of wickless-heat pipe as passive cooling system in nuclear spent fuel pool using RELAP5/MOD3. 2
MH Kusuma, NSD Putra, S Ismarwanti, S Widodo
International Journal on Advanced Science, Engineering and Information …, 2017
232017
Preliminary study on mass flow rate in passive cooling experimental simulation during transient using NC-queen apparatus
M Juarsa, JH Purba, HM Kusuma, T Setiadipura, S Widodo
Atom Indonesia 40 (3), 141-147, 2014
202014
Simulation of Operational Conditions of FASSIP-02 Natural Circulation Cooling System Experimental Loop
AR Antariksawan, S Widodo, M Juarsa, D Haryanto, MH Kusuma, N Putra
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear …, 2018
172018
Numerical study on natural circulation characteristics in FASSIP-02 experimental facility using RELAP5 code
AR Antariksawan, S Widodo, M Juarsa, D Haryanto, MH Kusuma, N Putra
IOP Conference Series: Earth and Environmental Science 105 (1), 012090, 2018
152018
Analisis konveksi alam teras reaktor TRIGA berbahan bakar tipe pelat menggunakan COOLOD-N2
KA Sudjatmi, EP Hastuti, S Widodo, R Nazar
Jurnal Teknologi Reaktor Nuklir TRI DASA MEGA 17 (2), 67-78, 2015
142015
Simulation of heat flux effect in straight heat pipe as passive residual heat removal system in light water reactor using RELAP5 Mod 3.2
MH Kusuma, N Putra, S Widodo, AR Antariksawan
Applied Mechanics and Materials 819, 122-126, 2016
132016
Design of passive residual heat removal systems and application of two-phase thermosyphons: A review
W Surip, N Putra, AR Antariksawan
Progress in Nuclear Energy 154, 104473, 2022
122022
TRIGA 2000 Research Reactor Thermal-hydraulic Analysis Using RELAP/SCDAPSIM/MOD3. 4
AR Antariksawan, E Umar, S Widodo, M Juarsa, MH Kusuma
International Journal of Technology 8 (4), 698-708, 2017
122017
Determining coolant flow rate distribution in the fuel-modified TRIGA plate reactor
EP Hastuti, S Widodo, MD Isnaini, SG Rina, B Syaiful
Journal of Physics: Conference Series 962 (1), 012045, 2018
102018
A Backward method to estimate the Dai-ichi reactor core damage using radiation exposure in the environment
PM Udiyani, S Kuntjoro, S Widodo
Atom Indonesia 42 (2), 63-70, 2016
92016
Performance analysis of AP1000 passive systems during Direct Vessel Injection (DVI) line break
AS Ekariansyah, S Widodo
Atom Indonesia 42 (2), 79-88, 2016
82016
Analysis of natural convection in TRIGA reactor core plate types fueled using COOLOD-N2
KA Sudjatmi, N Reinaldy, PH Endiah, W Surip
Jurnal Teknologi Reaktor Nuklir 17 (2), 67-78, 2015
82015
Penentuan koefisien dispersi atmosferik untuk analisis kecelakaan reaktor PWR di Indonesia
PM Udiyani, S Widodo
TRI DASA MEGA-JURNAL TEKNOLOGI REAKTOR NUKLIR 14 (2), 2012
82012
Analysis Of The Effect Of Elevation Difference Between Heater And Cooler Position In The Fassip-01 Test Loop Using Relap5
AS Ekariansyah, H Tjahjono, M Juarsa, S Widodo
SIGMA EPSILON-Buletin Ilmiah Teknologi Keselamatan Reaktor Nuklir 19 (1), 2016
72016
Preliminary investigation of natural circulation stability in FASSIP-01 experimental facility using RELAP5 code
AR Antariksawan, S Widodo, M Juarsa, G Giarno, MH Kusuma, N Putra
AIP Conference Proceedings 2001 (1), 2018
62018
Abnormal control rod withdrawal analysis for innovative research reactor using PARET-ANL codes
EP Hastuti, S Tukiran, S Widodo, Sudarmono
Kerntechnik 83 (2), 96-105, 2018
62018
The thermal-hydraulics analysis on radial and axial power fluctuation for AP1000 reactor
MD Isnaini, S Widodo, M Subekti
Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega 17 (2), 79-86, 2015
62015
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