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Published in The Conversations, 2021
Published in Atom Indonesia, 2021
To some extent, the diffusion approximation still works quite well to analyze the IPWR core model. Even though some discrepancies were observed in the results, the significantly low computational cost is a benefit that cannot be neglected in the diffusion method. Indeed, further improvement in the method used in this work is needed if one wants more accurate results for more reliable analysis.
Recommended citation: H. Ardiansyah and M. R. Oktavian, “Evaluating the Diffusion Approximation Capability on the Integral Pressurized Water Reactor (IPWR) Core Calculation,” Atom Indo., vol. 47, no. 2, p. 85, July 2021, doi: 10.17146/aij.2021.1013.
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Published in Journal of Physics: Conference Series, 2021
The neutronics simulation of the PBMR-400 using the deterministic core simulator AGREE with multigroup cross sections generated using the Monte Carlo code Serpent showed considerable improvement in the agreement with the full core Serpent result as the number of energy groups was increased. An eigenvalue improvement of approximately 530 pcm was observed when the number of energy groups was increased from 2 to 23. However, even with 7 energy groups sufficiently accurate results were obtained with could be considered acceptable for core analysis. Similar improvements were observed in the flux and power distributions as the number of energy groups were increased. Work is continuing on the incorporation of assembly discontinuity factors into the deterministic core calculation, as well as the analysis of calculations at the full range of core power and temperature conditions. This work will involve the assessment of using color set or supercell models at the various temperature conditions instead of relying on full core Monte Carlo for every branch calculation necessary for practical reactor simulation.
Recommended citation: H. Ardiansyah, V. Seker, T. Downar, S. Skutnik, and W. Wieselquist, “Evaluation of PBMR-400 Core Design Steady State Condition with Serpent and AGREE,” Journal of Physics: Conference Series, vol. 2048, p. 012024, Oct. 2021, doi: 10.1088/1742-6596/2048/1/012024.
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Published in BRIN Publishing, 2022
COVID-19 has disrupted all aspects of human life. To mitigate the impact of the pandemic, several efforts have been taken, including by Indonesian scholars abroad. This book entitled Indonesia Post-Pandemic Recovery Outlook: Strategy towards Net-Zero Emissions by 2060 from the Renewables and Carbon-Neutral Energy Perspectives explores energy sustainability and climate change issues and how it can progress further. There are also discussion on the delays caused by the COVID-19 pandemic to a few major renewable energy projects that should have been done in 2020-2021. Comprising of 14 chapters, this book is divided into three sections. The first part, Indonesia’s Current Position and Strategy for Renewable Energy, explores Indonesia’s current position and strategy on New and Renewable Energy. This chapter also explores Indonesia’s commitment towards Net-Zero Carbon Emission 2060. Second, Carbon-Free and Renewable Energy in Indonesia, discusses the status of renewable energy use in the world, elaborate on the carbon impact of energy shift from fossil to renewable sources, and introduce a new criterion in renewable energy: carbon-neutral energy. The last part, Indonesia’s New Strategy to Achieve Net-Zero Emission in 2060, explores the macroeconomic benefits of renewable and carbon-neutral energy deployment which are increasing energy security, fueling GDP development, creating job opportunities, enhancing human welfare, and achieving gender equality. We hope that this book can be a valuable reference for stakeholders, policymakers, as well as society to recover from the pandemic crisis and find better solutions to benefit future generations.
Recommended citation: D. F. Silalahi et al., Indonesia Post-Pandemic Outlook: Strategy towards Net-Zero Emissions by 2060 from the Renewables and Carbon-Neutral Energy Perspectives. Penerbit BRIN, 2022. doi: 10.55981/brin.562.
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Published in ASME Journal of Nuclear Engineering and Radiation Science, 2024
Various OFMSR core configurations with fixed volume have been studied using MCNP6.2 and Serpent-2 codes. It was apparent that radial blanket configuration generally showed a better neutronic performance than axial blanket configuration. Radial-1 possesses the better of the two radial configurations, with strongest negative TCR, longer Λ, and highest BR. In spite of marginally larger fuel inventory than its axial counterpart, Radial-1 still has the shortest DT. To obtain more optimized neutronic performance with fixed fuel salt volume, OFMSR is better using radial blanket configuration. Therefore, Radial-1 configuration is deemed as the neutronically optimum design among the models simulated in this study, and will be used for future design optimization.
Recommended citation: R. A. P. Dwijayanto, H. Ardiansyah, and A. W. Harto, “Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume,” Journal of Nuclear Engineering and Radiation Science, vol. 10, no. 3, p. 031301, July 2024, doi: 10.1115/1.4064465.
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Published in ANS Student Conference 2025, 2025
Neutron noise simulations for 2D rectangular geometries have been done for two cases, homogeneous reactor and C3 benchmark. The results agree with the analytical comparison and code-to-code comparison. For both cases, the ZPRTF shows a bell-shaped curve for the phase, with plateau visible in the magnitude. This behavior is expected in all cases. Overall, the simulation shows the effect of perturbation in a 2D system from a different perspective.
Recommended citation: H. Ardiansyah, “Neutron Noise Simulation in 2D Geometries,” presented at the ANS Student Conference 2025, University of New Mexico, 2025.
Published in The Conversations, 2025
Published in Nuclear Technology, 2026
Core diagnostics has been a key component of nuclear reactor operation to ensure reactor safety and performance. As a multicomponent system, perturbations in nuclear reactors are unavoidable. This article reviews neutron noise, and its definition and application to nuclear reactors. Our review finds that neutron noise has been integral to nuclear reactor operations. Multiple experiments using reactor data have been conducted to measure the perturbations that can happen to a nuclear reactor. Implementation of neutron noise analysis provides some insight into the perturbations that can happen in a reactor, effectively providing a means to diagnose all the phenomena in a nuclear reactor system. Seeing the benefits of conducting noise experiments, computational models of neutron noise have been developed. In the first years, the development focused on defining the neutron noise sources from reactor operations. Neutron noise theory and solutions were developed from the neutron transport theory for power reactor systems. This article reviews the derivation of neutron noise using diffusion theory, which simplifies neutron transport theory, and some computational tools developed to solve such problems. This article also reviews implementation of machine learning for neutron noise analysis. Although it has promising prospects, it still requires some available data from operating reactors or sufficiently high-fidelity simulations to train the model. Another area that can benefit from neutron noise analysis is diagnostics for Generation-IV (Gen-IV) reactors. As new types of reactors have been developed over the years, and especially with the development of Gen-IV reactors, new kinds of perturbations, which can happen to those systems, might arise. Some new methodologies could be developed to identify the noise sources in the systems of advanced reactors, and eventually implemented for computational analysis of neutron noise for advanced reactors.
Recommended citation: Ardiansyah, H., & Kozlowski, T. (2026). Review of Detecting Anomalies in Power Reactors Using Neutron Noise Analysis. Nuclear Technology, 1–22. https://doi.org/10.1080/00295450.2026.2619208
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Undergraduate course, Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois Urbana-Champaign, 2023
Role: Teaching Assistant to Prof. Tomasz Kozlowski.
Description: Assisting with grading and office hours
Undergraduate course, Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois Urbana-Champaign, 2024
Role: Teaching Assistant to Prof. April Novak.
Description: Assisting with grading and office hours
Graduate course, Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois Urbana-Champaign, 2024
Role: Teaching Assistant to Prof. April Novak.
Description: Assisting with grading and office hours
Undergraduate course, Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois Urbana-Champaign, 2025
Role: Teaching Assistant to Prof. April Novak.
Description: Assisting with grading and office hours
Undergraduate course, Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois Urbana-Champaign, 2025
Role: Teaching Assistant to Prof. Tomasz Kozlowski.
Description: Assisting with grading and office hours
Graduate course, Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois Urbana-Champaign, 2025
Role: Teaching Assistant to Prof. April Novak.
Description: Assisting with grading and office hours