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Nuri Trianti
Nuri Trianti
Research Center for Nuclear Reactor Technology, Nuclear Energy Research Organization, National
Verified email at brin.go.id
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Cited by
Year
ETSON-MITHYGENE benchmark on simulations of upward flame propagation experiment in the ENACCEF2 experimental facility
A Bentaïb, N Chaumeix, R Grosseuvres, B Alexandre, L Gastaldo, ...
12th International Topical Meeting on Reactor Thermal-Hydraulics, Operation …, 2018
112018
Design study of thorium-232 and protactinium-231 based fuel for long life BWR
N Trianti, Z Su’ud, ES Riyana
AIP Conference Proceedings 1448 (1), 96-100, 2012
82012
Design study of thorium cycle based long life modular boiling water reactors
N Trianti, Z Su’ud, ES Riyana
Indonesian Journal of Physics 22 (4), 133-137, 2011
82011
Nuclear energy contribution for net zero emission and national energy mix 2060 in Indonesia
S Permana, N Trianti, A Rahmansyah
Journal of Physics: Conference Series 2243 (1), 012066, 2022
62022
Preliminary design study of small long life boiling water reactor (BWR) with tight lattice thorium nitride fuel
N Trianti, Z Su'ud, I Arif, ES Riyana
AIP Conference Proceedings 1615 (1), 80-84, 2014
52014
Neutronic Performance of Small Long-Life Boiling Water Reactor Using Thorium as Fuel and the Addition of Protactinium as Burnable Poisons
N Trianti, Z Su’ud, I Arif, ES Riyana
Advanced Materials Research 772, 495-500, 2013
52013
Nuclear energy contribution potential to secure electricity demand with low carbon emission and low risk of power plant in Indonesia
S Permana, N Trianti, A Rahmansyah
IOP Conference Series: Earth and Environmental Science 753 (1), 012048, 2021
42021
Comparison of thermal-hydraulic calculation in 100 MWt thorium-based HTGR using SiC and ZrC TRISO coated fuel particle
F Miftasani, N Widiawati, N Trianti, DS Salsabila, T Setiadipura, ...
Nuclear Engineering and Design 412, 112463, 2023
32023
Optimum power determination and comparison of multi-pass and OTTO fuel management schemes of HTGR-based PeLUIt reactor
N Trianti, N Widiawati, C Wulandari, F Miftasani, A Rohanda, A Khakim, ...
Nuclear Engineering and Design 415, 112696, 2023
22023
Neutronic design performance of 100 MWe MSR with thorium-enriched uranium and thorium-plutonium-minor actinide fuel
C Wulandari, N Trianti, S Permana, A Waris
Nuclear Engineering and Design 414, 112646, 2023
22023
Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer
F Miftasani, N Widiawati, N Trianti, T Setiadipura, Z Zuhair, D Irwanto, ...
Kerntechnik 88 (4), 503-517, 2023
22023
Power Flattening on Design Study of Small Long-Life Boiling Water Reactor (BWR) with Tight Lattice Thorium Nitride Fuel
N Trianti, S Zaki, I Arif, S Permana, ES Riyana
Applied Mechanics and Materials 751, 257-262, 2015
22015
Neutronic performance evaluation of Plutonium Recycling in two core sizes for a 250 MWt Molten salt reactor
C Wulandari, N Trianti, S Permana, M Kinoshita, A Waris
Nuclear Engineering and Design 415, 112733, 2023
12023
Analysis of core configuration for conceptual gas cooled fast reactor (GFR) using OpenMC
I Karomah, AM Mabruri, RD Syarifah, N Trianti
Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega 25 (2), 85-90, 2023
12023
Filtration efficiency analysis of cotton cloth-based mask for reducing transmission rate of COVID-19 using PM2. 5 detection methods
S Permana, N Trianti
Journal of Physics: Conference Series 2243 (1), 012067, 2022
12022
Burnable Poison Neutronic Characteristics of Hexagonal Tight Lattice Cell for Small Long-Life BWR with Thorium Based Fuel
N Trianti, Z Su’ud, I Arif, S Permana, ES Riyana
The 4 th International Conference on Theoretical and Applied Physics (ICTAP …, 0
1
Investigating geometry adjustments for enhanced performance in a PeLUIt-10 MWt pebble bed HTGR with OTTO refueling scheme
F Miftasani, RAP Dwijayanto, G Abrar, N Widiawati, N Trianti, ...
Nuclear Engineering and Design 422, 113163, 2024
2024
Neutronic and thermal-hydraulic analysis for TRIGA Mark II in subcooled nucleate boiling condition
N Trianti, P Basuki, A Maulana, JS Pane, E Umar, Z Su'ud
Nuclear Engineering and Design 421, 113092, 2024
2024
Validation of OpenMC Code Criticality Value Calculation for GFR Reactor with UN-PuN Fuel
F Prasetya, AM Mabruri, I Karomah, RD Syarifah, IK Aji, N Trianti
Journal of Physics: Conference Series 2734 (1), 012065, 2024
2024
Subcooled boiling prediction on current fuel configuration of TRIGA 2000 reactor core by COOLOD-N2 code
N Trianti, P Basuki, A Maulana, ARI Suwarso, Z Su’ud
AIP Conference Proceedings 2967 (1), 2024
2024
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