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Analysis of the advanced PWR cell MOX fuel using SiC, Zr, FeCrAl, and SS-310 as cladding materials

AIP Conference Proceedings, 2024, Vol.2967 (1)

2024

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Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo code

Nuclear Engineering and Technology, 2023, 55(5), , pp.1775-1782

2023

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Transient calculation on TRIGA 2000 of plate-type fuel element using RELAP5, EUREKA2/RR, and MTR-DYN codes

Nuclear technology & radiation protection, 2021-01, Vol.36 (3), p.211-218

2021

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Sensitivity of Reflector on Neutronic Parameter for Conversion Core Design of the TRIGA Research Reactor

Journal of physics. Conference series, 2019-04, Vol.1198 (2), p.22059

2019

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An Improved Steady-State and Transient Analysis of the RSG-GAS Reactor Core under RIA Conditions Using MTR-DYN and EUREKA-2/RR Codes

Science and Technology of Nuclear Installations, 2022-07, Vol.2022, p.1-12

2022

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Reactivity Coefficient Calculation for AP1000 Reactor Using the NODAL3 Code

Journal of physics. Conference series, 2018-02, Vol.962 (1), p.12057

2018

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Reactivity insertion accident analysis during uranium foil target irradiation in the RSG-GAS reactor core

Nuclear technology & radiation protection, 2020-01, Vol.35 (3), p.201-207

2020

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Analysis of NEA-NSC PWR Uncontrolled Control Rod Withdrawal at Zero Power Benchmark Cases with NODAL3 Code

Science and Technology of Nuclear Installations, 2017-01, Vol.2017, p.1-8

2017

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NODAL3 Sensitivity Analysis for NEACRP 3D LWR Core Transient Benchmark (PWR)

Science and Technology of Nuclear Installations, 2016-01, Vol.2016, p.1-11

2016

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Verification of NODAL3 code with PWR MOX/UO2 core transient benchmark

Nuclear engineering and design, 2024-08, Vol.424, p.113326, Article 113326

2024

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Neutronic characteristics analysis of accident tolerant fuel and claddings for fuel assembly of light water reactor

AIP Conference Proceedings, 2024, Vol.2967 (1)

2024

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The Verification of Coupled Neutronics Thermal-Hydraulics Code NODAL3 in the PWR Rod Ejection Benchmark

Science and Technology of Nuclear Installations, 2014-01, Vol.2014, p.1-9

2014

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CALCULATION OF 2-DIMENSIONAL PWR MOX/UO2 CORE BENCHMARK OECD NEA 6048 WITH SRAC CODE

Jurnal teknologi reaktor nukir Tri Dasa Mega, 2020-09, Vol.22 (3), p.89

2020

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CFD simulation on sub-channel blockage in the fuel plate of RSG-GAS reactor

Progress in nuclear energy (New series), 2024-05, Vol.170, p.105155, Article 105155

2024

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Control rods’ position history effect on the Indonesian multipurpose research reactor RSG-GAS operation and safety parameters

Progress in nuclear energy (New series), 2023-02, Vol.156, p.104552, Article 104552

2023

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Neutronic parameters analysis of a PWR fuel element using silicon carbide claddings with SRAC2006/NODAL3 codes

AIP Conference Proceedings, 2019, Vol.2180 (1)

2019

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Analysis of the excess reactivity and control rod worth of RSG-GAS equilibrium silicide core using Continuous-Energy Monte Carlo Serpent2 code

Annals of nuclear energy, 2021-05, Vol.154, p.108107, Article 108107

2021

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Burnup determination of Full-Scale, High-Density U3Si2-Al (4.8 gU/cc) fuel plate using destructive radiochemical technique

Nuclear engineering and design, 2024-08, Vol.425, p.113327, Article 113327

2024

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Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo code

Nuclear engineering and technology, 2023, Vol.55 (5), p.1775-1782

2023

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Evaluation of Kinetic Parameters RSG-GAS Reactor Equilibrium Silicide Core Using Continuous-Energy Monte Carlo Serpent 2 Code

Nuclear science and engineering, 2024-01, p.1-15

2024

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