Sofrany Ekariansyah
Sofrany Ekariansyah
Email yang diverifikasi di batan.go.id
Judul
Dikutip oleh
Dikutip oleh
Tahun
Fuzzy probability based fault tree analysis to propagate and quantify epistemic uncertainty
JH Purba, DTS Tjahyani, AS Ekariansyah, H Tjahjono
Annals of Nuclear Energy 85, 1189-1199, 2015
322015
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
62016
Performance analysis of AP1000 passive systems during Direct Vessel Injection (DVI) line break
AS Ekariansyah, S Widodo
Atom Indonesia 42 (2), 79-88, 2016
42016
Benchmarking of experimental setup for pressure drop calculation in a packed pebble bed using RELAP5
AS Ekariansyah, S Widodo
Journal of Physics: Conference Series 1198 (2), 022033, 2019
32019
Preliminary analysis of core temperature distribution of experimental power reactor using RELAP5
AS Ekariansyah, S Widodo, H Tjahjono, S Susyadi, PI Wahyono, ...
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 20 (3), 159-165, 2018
32018
RELAP5 SIMULATION FOR SEVERE ACCIDENT ANALYSIS OF RSG-GAS REACTOR
AS Ekariansyah, EP Hastuti, S Sudarmono
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 20 (1), 23-34, 2018
32018
PRELIMINARY STUDY ON RELAP5 SIMULATION OF DVI LINE BREAK ACCIDENT IN THE ATLAS FACILITY USING BEST ESTIMATE PLUS UNCERTAINTY METHOD
AS Ekariansyah, S Widodo
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 19 (1), 19-32, 2017
22017
Corrigendum to “Fuzzy probability based fault tree analysis to propagate and quantify epistemic uncertainty”[Ann. Nucl. Energy 85 (2015) 1189–1199]
JH Purba, DTS Tjahyani, AS Ekariansyah, H Tjahjono
Annals of Nuclear Energy 111, 716-717, 2018
12018
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
2020
Investigation of RDE thermal parameters during DLOFC in the absence of water inside the Reactor Cavity Cooling System
H Tjahjono, R Kusumastuti, AS Ekariansyah, MH Kusuma, M Susmikanti
Journal of Physics: Conference Series 1493, 012004, 2020
2020
Analysis on inadvertent operation of decay heat removal system in NuScale reactor
Susyadi, AS Ekariansyah, H Tjahjono, DTS Tjahyani
AIP Conference Proceedings 2180 (1), 020014, 2019
2019
Analysis of MOD-1 heating section efficiency in the RCCS test facility of high temperature reactors
H Tjahjono, R Kusumastuti, M Juarsa, D Haryanto, S Widodo, ...
AIP Conference Proceedings 2180 (1), 020022, 2019
2019
Thermal-hydraulic benchmarking of RSG-GAS research reactor using RELAP5
EP Hastuti, AS Ekariansyah, Sudarmono, Sujarwono, S Wetchagarun
AIP Conference Proceedings 2180 (1), 020025, 2019
2019
Simulation of nuclear steam supply system of experimental power reactor
AS Ekariansyah, M Subekti, S Widodo
AIP Conference Proceedings 2180 (1), 020008, 2019
2019
DEVELOPMENT OF EXPERIMENTAL POWER REACTOR (EPR) MODEL FOR SAFETY ANALYSES USING RELAP5
AS Ekariansyah, M Subekti, S Widodo, H Tjahjono, S Susyadi, ...
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 21 (2), 51-58, 2019
2019
Two Dimensional Performance Analysis of Small HTR Residual Heat Removal System in DLOFC Condition
H Tjahjono, S Widodo, AR Antariksawan, A Sofrany, H Kusuma, ...
Journal of Physics: Conference Series 1198 (2), 022042, 2019
2019
Transient Analysis of CVCS Malfunction in Large Passive PWR
S Widodo, AS Ekariansyah
Journal of Physics: Conference Series 1198 (2), 022016, 2019
2019
MODELLING OF RSG-GAS HEAT EXCHANGER FOR STEADY-STATE SIMULATION
AS Ekariansyah
SIGMA EPSILON-Buletin Ilmiah Teknologi Keselamatan Reaktor Nuklir 22 (1), 2018
2018
Main steam line break accident simulation of APR1400 using the model of ATLAS facility
AS Ekariansyah, GR Sunaryo
Journal of Physics: Conference Series 962 (1), 012037, 2018
2018
ANALISIS KONDISI TERAS REAKTOR DAYA MAJU AP1000 PADA KECELAKAAN SMALL BREAK LOCA
AS Ekariansyah
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 17 (2), 87-98, 2015
2015
Sistem tidak dapat melakukan operasi ini. Coba lagi nanti.
Artikel 1–20