Accuracy of Batan-3DIFF and MCNP6 codes for thermal neutron flux distribution at the irradiation position of RSG-GAS reactor

S Pinem, TM Sembiring - International Journal of Nuclear …, 2019 - inderscienceonline.com
This paper presents the accuracy of the neutron diffusion and Monte Carlo methods in
determining the axial thermal neutron flux in the irradiation facility. The calculations are …

[PDF][PDF] Analysis of fuel temperature reactivity coefficient of the PWR using WIMS code

SP Rajagukguk, S Bahkri… - … Reaktor Nuklir Tri Dasa …, 2022 - pdfs.semanticscholar.org
The Fuel Temperature Reactivity Coefficient (FTRC) is an important parameter in design,
control, and safety, particularly in PWR reactor. It is then very important to validate any new …

[PDF][PDF] Neutronic Analysis of the RSG-GAS Fuel Using Burnable Poison

M Ridho, HB Santosa… - … Reaktor Nuklir Tri …, 2023 - eresources.poltekkes-smg.ac.id
Control and safety of nuclear reactors are significantly influenced by the determination of
safety parameters. The three most crucial safety factors for assessing reactor status are the …

Neutron Radiation Damage Estimation in the Core Structure Base Metal of RSG GAS

SA Santa - Journal of Physics: Conference Series, 2018 - iopscience.iop.org
Radiation damage in core structure of the Indonesian RGS GAS multi purpose reactor
resulting from the reaction of fast and thermal neutrons with core material structure was …

[PDF][PDF] Neutronic analysis of the VVER-1200 lattice cell fuel using WIMSD-5B code

SP Rajagukguk, S Bakhri, A Muliyana… - … NUKLIR TRI DASA …, 2022 - scholar.archive.org
The calculation of safety parameters in nuclear reactors has an important influence on
nuclear reactor control and safety. The infinite multiplication factor, reactivity coefficients, and …

[PDF][PDF] ANALYSIS OF THORIUM PIN CELL BURN UP OF THE PWR USING WIMS CODE

JH Panggabean, SP Rajagukguk, S Bakhri - Jurnal Teknologi Reaktor …, 2022 - core.ac.uk
A thorium-fueled benchmark comparison was made in this study between state-of-the-art
codes, WIMSD-5B code to MOCUP (MCNP4B+ ORIGEN2), and CASMO-4 for burnup …

[PDF][PDF] ANALYSIS OF THE PPF VALUE DEPENDENCE ON THE FUEL BURNUP

L Suparlina, P Purwadi… - Jurnal Teknologi Reaktor …, 2022 - scholar.archive.org
The RSG-GAS reactor has been operated in a safe and reliable manner for about 35 years
since it commenced its operation in 1987 to serve radioisotopes production, NAA, neutron …

[PDF][PDF] Analysis of reactivity insertion as a function of the RSG-GAS fuel burn-up

T Surbakti, S Pinem, L Suparlina - JURNAL TEKNOLOGI REAKTOR …, 2021 - academia.edu
Analysis of the control rod insertion is important as it is closely related to reactor safety.
Previously, the analysis has been carried out in RSGGAS during static condition, not as a …

Analysis of the reactivity coefficient of the PWR thorium fuel

SP Rajagukguk, S Bakhri - Jurnal Teknologi Reaktor Nuklir, 2024 - inis.iaea.org
[en] In design, control, and safety, especially in Pressurized Water Reactors, the Reactivity
Coefficient parameter is crucial. The validation of every new library for an accurate …

[PDF][PDF] ANALISIS MANAJEMEN BAHAN BAKAR DESAIN TERAS KONVERSI TRIGA 2000

L Suparlina, T Surbakti - SIGMA EPSILON-Buletin Ilmiah …, 2021 - scholar.archive.org
CONVERSION CORE. The board benefits of using research reactors have led many
countries to build new research reactors. The current trend is a multipurpose reactor type …