Suwoto

Scopus Publications

Optimizing hydrogen production through SOEC-PeLUIt-40 coupling: a sustainable approach to clean energy generation
Sriyono Sriyono, Dedy Priambodo, Marliyadi Pancoko, Topan Setiadipura, Djati Hoesen Salimy, Ign. Djoko Irianto, Sukmanto Dibyo, Mohammad Dhandhang Purwadi, Yus Rusdian Akhmad, Zuhair, Suwoto, Rahayu Kusumastuti, Erlan Dewita, Siti Alimah, Geni Rina Sunaryo, Entin Hartini, Nurul Huda, Farisy Yogatama Sulistyo
Nuclear Engineering and Design, 2025
Neutronic investigation of VVER-1000 assembly with mixed plutonium–uranium nitride fuel
Zuhair, R. Andika Putra Dwijayanto, Nina Widiawati, Fitria Miftasani, Nuri Trianti, et al.
Indian Journal of Physics, 2025
Radiation safety analysis of a generic 2 MCi multipurpose gamma irradiator
Hery Adrial, Anis Rohanda, Azizul Khakim, Suwoto Suwoto, Sukmanto Dibyo, Zuhair Zuhair, Muksin Aji Setiawan, Lily Suparlina, Daddy Setyawan
Applied Radiation and Isotopes, 2025
Implementation of thorium-based fuel for Indonesia Micro Reactor (IMR)
Erlan Dewita, Suwoto, Zuhair, Sriyono, Mohammad Dhandhang Purwadi, Sudi Ariyanto, Yarianto Sugeng Budi Susilo, Farisy Yogatama Sulistyo
Nuclear Engineering and Design, 2024
NEUTRONIC INVESTIGATION ON THORIUM MOX FUEL IN VVER-1000 REACTOR ASSEMBLY
Zuhair, W. Luthfi, R.A.P. Dwijayanto, M.D. Isnaini, Suwoto
Latvian Journal of Physics and Technical Sciences, 2024
The accumulation of plutonium produced by LWR operations causes public concern related to its radiotoxicity and proliferation issue. Therefore, there is some interest in developing various methods for consuming plutonium through plutonium incineration i.e., by utilising thorium-based nuclear fuel. Thorium-plutonium mixed oxide fuel (Thorium MOX) is an attractive option considered for plutonium incineration. The aim of the study is to investigate the neutronic characteristics of Thorium MOX fuel in VVER-1000 nuclear reactor fuel assemblies. The VVER-1000 Benchmark model was utilised in the present study. A series of calculations were performed with the MCNP6 code and the ENDF/B-VII library. The calculation results show that a proper increase in Pu content could increase k inf of ThMOX fuel, so it could have almost the same k inf with MOX fuel or increase Pu content when needed. It was also shown that Thorium MOX fuel assembly had more negative Doppler reactivity due to neutron capture by thorium (232Th). The moderator temperature coefficient was found to be more negative than the Doppler coefficient, and it could be concluded that replacing uranium with thorium could reduce the amount of plutonium produced while increasing plutonium consumption.
Study on neutronic behavior of VVER-1000 fuel assembly with duplex fuel rod design
Zuhair, Wahid Luthfi, Hery Adrial, Azizul Khakim, Suwoto
Nuclear Engineering and Design, 2024
MCNP performance on neutronic calculation of VERA benchmark cases
Zuhair, Zuhair, Luthfi, Wahid, Entin Hartini, Sriyono, Sriyono, Suwoto, Suwoto, et al.
Journal of Theoretical and Applied Physics, 2024
THE EFFECT OF BURNABLE ABSORBERS ON CRITICALITY AND REACTIVITY COEFFICIENT OF VVER-1000 ASSEMBLY
Z Zuhair, Wahid Luthfi, Muhammad Isnaini, S Sriyono, S Suwoto
Nuclear Technology and Radiation Protection, 2024
Burnable absorbers play an important role in nuclear reactor safety and exploring their effect on the reactor core behavior is an important issue in the design and operation of the reactor core. The aim of the present work was to discover the effect of burnable absorbers on criticality and reactivity coefficient of VVER-1000 assembly. The calculations were conducted with a 3-D Monte Carlo transport code MCNP6 and ENDF/B-VII.1 nuclear library. The Gd2O3 content varying from 0 wt.% to 8 wt.% was considered to complete the inter-comparison analysis between the criticality and the reactivity coefficients for three UO2+Gd2O3 fuel configurations. At the beginning of the cycle, there is a significant difference between the criticality (kinf) of assembly with and without Gd2O3, however, at the middle of the cycle those differences become very small and almost the same at the end of the cycle. The Doppler temperature coefficient values are always sufficiently negative and demonstrate a more negative trend with increasing gadolinium concentrations and fuel burnup. At beginning of the cycle, the moderator temperature coefficient value increases negatively as gadolinium concentration increases but, at middle of the cycle this trend does not occur. The fuel composition is predicted to be the reason behind this situation. At the end of cycle, there is no clear trend in the moderator temperature coefficient values with respect to Gd2O3 concentration. The absorbing effect of Gd2O3 appears to have diminished significantly. Overall, this research provides insights into the influence of the burnable absorbers on the neutronic parameters of the VVER-1000 assembly and its contribution to reactor safety.
Optimization of the UO2-Gd2O3 Fuel Assembly Arrangement Pattern in the SMR-NuScale Reactor
Hery Adrial, Suwoto Suwoto, Muhammad Budi Setiawan, Ihda Husnayani, Zuhair Zuhair
Aip Conference Proceedings, 2024
Small-scale Modular Reactor (SMR) is a type of PWR reactor that is currently developing. The NuScale reactor with a power of 160 MWt which is included in the SMR category provides space for researchers to develop the fuel assembly. This research was conducted with the aim of Optimization the arrangement of the NuScale reactor fuel assembly pattern using the MCNP 6 code with the ENDF/B-VII library. There are several types of fuel assembly in NuScale reactors. One of the fuel assemby that is focused on in this research is a fuel assembly that contains fresh UO2− Gd2O3 with an enrichment of 4.55% and has a Gd content of 8%. In order to optimize the arrangement pattern of the UO2−Gd2O3 fuel assembly, the infinity criticality and reactivity coefficients were calculated using the arrangement patterns of 32, 24, 16 and 8 Burnable Poisson. From the results of the research, the optimum number of Burnable Poissons in the fuel assembly is 24 pins for 8% Gd2O3. It is hoped that the results of the research can be used as complementary materials for complete neutronic calculations, safety parameters and analysis on the NuScale nuclear reactor core.
Neutronic Investigation of Integral Burnable Absorber (UO2-Gd2O3) Different Pattern Arrangement on Nuscale Reactor Fuel Assembly
Suwoto Suwoto, Hery Adrial, Wahid Luthfi, Topan Setiadipura, Zuhair Zuhair
Aip Conference Proceedings, 2024
The neutronic effect of location arrangement burnable absorber rod such as gadolinia (Gd2O3) on the reactivity control of integral Pressurized Water Reactor (iPWR) Nuscale reactor have been investigated. Ten fuel assemblies of 17x17 matrix array with different location arrangement and two gadolinia concentration were done. One Fuel Assembly (FA) was assumed as standard one and nine of FAs were analyzed containing of 2% and 8% gadolinia concentration on 32 burnable absorber fuel rods (UO2-Gd2O3) which placed it in different location of each FAs were investigated. The design of the Nuscale Fuel Assembly (FA) for the iPWR was created using the MCNP6 code to develop a 3D model. This was combined with the ENDF/B-VII.1 continuous nuclear data library. All calculations were done on Hot Full Power (HFP) and Hot Zero Power (HZP) condition. This article examines the neutronic characteristics of two types of Fuel Assemblies with UO2 enrichment of 4.55% 235U and differences concentration of 2% and 8% gadolinia as an integral fuel burnable absorber rods (UO2-Gd2O3), respectively. According to the calculation results, the discrepancy of the Doppler temperature coefficient of the fuel is relatively low compared to the standard assumption, i.e. -0.0476 to -2,989%Δk/k/K and -0.0749 to -4.25% Δk/k/K for 2% and 8% gadolinia concentration on an integral burnable absorber (UO2−Gd2O3) in different location arrangement, respectively. It was found that the different loading patterns arrangement of integral burnable absorber fuel (UO2-Gd2O3) in the Nuscale reactor FA show did not significantly affect the temperature reactivity coefficient value. The calculated results for both the Doppler temperature coefficient (DTC) and moderator temperature coefficient (MTC) indicate that their values fall within the range of the reference design value.
Study on neutronic characteristics of NuScale reactor core with thorium coating
Zuhair Zuhair, Wahid Luthfi, Nina Widiawati, Suwoto Suwoto, Topan Setiadipura
Aip Conference Proceedings, 2023
STUDY ON KINETIC PARAMETERS OF PEBBLE BED REACTOR WITH TRISO DUPLEX FUEL
Z Zuhair, Wahid Luthfi, Andika Dwijayanto, Anis Rohanda, S Suwoto
Nuclear Technology and Radiation Protection, 2023
INVESTIGATION ON NEUTRONIC BEHAVIOR OF PEBBLE BED REACTOR FOR TRU TRANSMUTATION
Zuhair Zuhair, Wahid Luthfı, R. Andika Putra Dwijayanto, Suwoto Suwoto, Zaki Su’ud
Romanian Journal of Physics, 2023
Transmutation of Plutonium and Minor Actinide in PWR Thorium-Transuranic Fuel Assembly
- Zuhair, Wahid Luthfi, R. Andika Putra Dwijayanto, - Sriyono, - Suwoto
International Journal on Advanced Science Engineering and Information Technology, 2023
Analysis of Neutron Flux Distribution of 160 MWth PWR NPP Reactor Using MCNP
Amir Hamzah, Suwoto, Hery Adrial, Pande Made Udiyani, Muhammad Budi Setiawan, Entin Hartini
Aip Conference Proceedings, 2022
Preliminary study on TRU transmutation in VVER-1000 fuel assembly using MCNP6
Zuhair, R. Andika Putra Dwijayanto, Sriyono, Suwoto, Zaki Su’ud
Kerntechnik, 2022
STUDY ON KINETIC PARAMETERS CHARACTERISTICS OF PEBBLE BED REACTOR USING HTR-PROTEUS FACILITY
Z Zuhair, Wahid Luthfi, S Sriyono, S Suwoto, Topan Setiadipura
Nuclear Technology and Radiation Protection, 2022
Study Analysis of Multiplication Factor on ADS Transmutation System
Sudarmono, E P Hastuti, A Rohanda, A S Ekariansyah, Y Kasesaz, Suwoto
Journal of Physics Conference Series, 2022
The effects of U-233 impurity on U-232 and Tl-208 buildup in experimental power reactor with thorium-based fuel
R A P Dwijayanto, Suwoto, Zuhair, Z Su’ud
Journal of Physics Conference Series, 2021
Preliminary analysis on burnup calculation of several arrangement of TRISO and pebble inside an MCNP model of HTR core
W Luthfi, Suwoto, T Setiadipura, Zuhair
Journal of Physics Conference Series, 2021
Impact of different nuclear data library on control rod reactivity worth calculation of small pebble bed reactor
Suwoto, H Adrial, T Setiadipura, Zuhair, S Bakhri
Journal of Physics Conference Series, 2021
Optimization of PeLUIt-150 conceptual design
T Setiadipura, W Luthfi, S Bakhri, Suwoto, Zuhair, Z Li, Y Sun
Journal of Physics Conference Series, 2021
Investigation on criticality and burnup performance of pebble bed reactor with thorium-based nuclear fuel
Philippine Journal of Science, 2021
Pebble Bed High Temperature Reactor for Electric and Cogeneration Application
T. Setiadipura, D. Irwanto, Suwoto, Zuhair
Journal of Physics Conference Series, 2021
Study on Control Rod Reactivity of Small Pebble Bed Reactor with Wallpaper Fuel Design
Zuhair, Suwoto, S. Permana, T. Setiadipura
Journal of Physics Conference Series, 2021
Analysis of water ingress accident in the RDE core using MCNPX
T Taryo, Zuhair, T Setiadipura, Suwoto, J C Kuijper
Journal of Physics Conference Series, 2021
Criticality Study on Different Pebble Arrangement inside HTR Reactor Core
L Wahid, T Setiadipura, Zuhair, Suwoto, S Bakhri
Journal of Physics Conference Series, 2021
Swing reactivity calculation of accelerator driven system subcritical reactor 100 mwth
Sudarmono, Suwoto, A. Rohanda, EP. Hastuti, Y. Kasezas
Journal of Physics Conference Series, 2020
Study on MCNP6 model in the calculation of kinetic parameters for pebble bed reactor
. Zuhair, . Suwoto, Topan Setiadipura, Zaki Su'ud
Acta Polytechnica, 2020
Neutronic effect of utilizing TRIZO particles on core characteristics of experimental power reactor
Zuhair, R. A. P. Dwijayanto, H. Adrial, Suwoto, T. Setiadipura
Aip Conference Proceedings, 2019
Effect of boron impurity and graphite thermal neutron scattering on criticality calculation of Indonesian experimental power reactor
Suwoto, H. Adrial, W. Luthfi, T. Setiadipura, Zuhair
Aip Conference Proceedings, 2019
Analysis on water ingress volume effect of the RDE core to criticality
Hery Adrial, Suwoto, Pande Made Udiyani, Amir Hamzah, Zuhair
Aip Conference Proceedings, 2019
The effects of fuel type on control rod reactivity of pebble-bed reactor
Zuhair, Suwoto, Topan Setiadipura, Jim C. Kuijper
Nukleonika, 2019
Study on the Characteristics of Effective Delayed Neutron Fraction (β eff) for Pebble-Bed Reactor with Plutonium Fuel
Zuhair, Suwoto, Topan Setiadipura, Jim C. Kuijper
Iranian Journal of Science and Technology Transaction A Science, 2019
Preliminary analysis of dose rates distribution of experimental power reactor 10 MW using MCNP
Amir Hamzah, Suwoto, Hery Adrial
Journal of Physics Conference Series, 2019
Equilibrium Core Design of Reaktor Daya Eksperimental
T Setiadipura, Suwoto, Zuhair
Journal of Physics Conference Series, 2019
Burnup Calculation Study of Pebble Bed Equilibrium Core
L. Suparlina, T. Setiadipura, Suwoto
Journal of Physics Conference Series, 2019
Sensitivity of heat transfer parameters on the Reaktor Daya Eksperimental - RDE core
Sudarmono, Suwoto, Syaiful Bakhri
Journal of Physics Conference Series, 2019
Control Rod Reactivity Analysis of One Stuck Rod Condition in 10 MWth Experimental Reactor Conceptual Design (RDE-10 MWth) on First Full Core
H. Adrial, Suwoto, A. Hamzah, Zuhair
Journal of Physics Conference Series, 2019
Study on MOX Core Characteristics of Experimental Power Reactor using MCNP6 Code
Zuhair, Suwoto, H. Adrial, T. Setiadipura
Journal of Physics Conference Series, 2019
Analysis of Heavy Metal Loading Optimization Through Criticality Calculation on RDE
Suwoto, H. Adrial, Zuhair, K. Kamajaya, S. Bakhri
Journal of Physics Conference Series, 2019
Criticality and Burnup Study on Different TRISO Modelling of HTR Pebble
L Wahid, T Setiadipura, Zuhair, Suwoto, S Bakhri
Journal of Physics Conference Series, 2019
Study on temperature coefficient of reactivity for pebble bed reactor with thorium fuel
International Journal of Mechanical Engineering and Technology, 2018
Neutron Radiation Damage Estimation in the Core Structure Base Metal of RSG GAS
S A Santa, Suwoto
Journal of Physics Conference Series, 2018
Steady State Temperature Distribution Investigation of HTR Core
Sudarmono, Suwoto, Syaiful Bakhri, Geni Rina Sunaryo
Journal of Physics Conference Series, 2018
Study on Characteristic of Temperature Coefficient of Reactivity for Plutonium Core of Pebbled Bed Reactor
Zuhair, Suwoto, T. Setiadipura, S. Bakhri, G.R. Sunaryo
Journal of Physics Conference Series, 2018
Power Peaking Effect of OTTO Fuel Scheme Pebble Bed Reactor
T. Setiadipura, Suwoto, Zuhair, S. Bakhri, G.R. Sunaryo
Journal of Physics Conference Series, 2018
Neutron dose rate analysis on HTGR-10 reactor using Monte Carlo code
Suwoto, H. Adrial, A. Hamzah, Zuhair, S. Bakhri, G. R. Sunaryo
Journal of Physics Conference Series, 2018
Neutron Fluence and DPA Rate Analysis in Pebble-Bed HTR Reactor Vessel Using MCNP
Amir Hamzah, Suwoto, Anis Rohanda, Hery Adrial, Syaiful Bakhri, Geni Rina Sunaryo
Journal of Physics Conference Series, 2018
The effects of applying silicon carbide coating on core reactivity of pebble-bed HTR in water ingress accident
Zuhair, Suwoto, T. Setiadipura, Z. Su’ud
Kerntechnik, 2017
Implementation of extended wood-saxon potential in 232Th nuclear fission mass yield calculation
A. Waris, Y. S. Perkasa, R. Kurniadi, Suwoto
International Conference on Instrumentation Communication Information Technology and Biomedical Engineering 2009 Icici Bme 2009, 2009

Suwoto

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Scopus Publications