Search Results - "Hong, Liem Peng"

Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo code by Pinem, Surian, Luthfi, Wahid, Liem, Peng Hong, Hartanto, Donny

“…Several reactor physics commissioning experiments were conducted to obtain the neutronic parameters at the beginning of the G.A. Siwabessy Multi-purpose…”
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Nuclear data sensitivity and uncertainty analyses on the first core criticality of the RSG GAS multipurpose research reactor by Liem, Peng Hong, Zuhair, Hartanto, Donny

“…The results of criticality, sensitivity and uncertainty (S\U) analyses on the first core criticality of the Indonesian 30 MWth Multipurpose Reactor RSG GAS…”
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Benchmarking the new ENDF/B-VIII.0 nuclear data library for OECD/NEA medium 1000 MWth sodium-cooled fast reactor by Hartanto, Donny, Khuwaileh, Bassam, Liem, Peng Hong

“…This paper presents the benchmark evaluation of the new ENDF/B-VIII.0 nuclear library for the OECD/NEA Medium 1000 MWth Sodium-cooled Fast Reactor (SFR). There…”
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Benchmarking the new ENDF/B-VIII.0 nuclear data library for the first core of Indonesian multipurpose research reactor (RSG GAS) by Hartanto, Donny, Gillette, Victor, Sembiring, Tagor Malem, Liem, Peng Hong

“…The Indonesian Multipurpose Research Reactor namely Reaktor Serba Guna G.A. Siwabessy (RSG GAS) is a 30 MWth (max.) pool-type reactor loaded with plate-type…”
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Preliminary investigation on the sodium fast reactor concave cores with near‐zero or negative sodium void reactivity by Liem, Peng Hong, Tahara, Yoshihisa, Takaki, Naoyuki

“…Summary A preliminary investigation on the sodium fast reactor (SFR) concave cores was conducted with the aim of obtaining near‐zero or negative sodium void…”
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Analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS using the Serpent Monte Carlo code and the ENDF/B-VIII.0 nuclear data library by Hartanto, Donny, Liem, Peng Hong

“…This paper presents the neutronics benchmark analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS (Reaktor Serba Guna G.A…”
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Performance indices optimization of long‐lived fission products transmutation in fast reactors by Liem, Peng Hong, Tahara, Yoshihisa, Takaki, Naoyuki, Hartanto, Donny

“…Summary An investigation on the nuclear transmutations of elemental long‐lived fission products (LLFPs) in a fast reactor is being conducted in Japan, focusing…”
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Design of Cesium target assembly with YH2 moderator and Gd thermal neutron shielding to produce 135Cs for LLFP transmutation study using the experimental fast reactor Joyo by Tahara, Yoshihisa, Liem, Peng Hong, Takaki, Naoyuki, Chiba, Satoshi

“…•Design of cesium target assembly to produce 135Cs in Joyo.•Irradiation fields with properly adjusted neutron spectra are proposed.•Natural Cs is used as a…”
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Neutronics design of VVER-1000 fuel assembly with burnable poison particles by Tran, Hoai-Nam, Hoang, Van-Khanh, Liem, Peng Hong, Hoang, Hung T.P.

“…This paper presents neutronics design of VVER-1000 fuel assembly using burnable poison particles (BPPs) for controlling excess reactivity and pin-wise power…”
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Design optimization of a new homogeneous reactor for medical radioisotope Mo-99/Tc-99m production by Liem, Peng Hong, Tran, Hoai Nam, Sembiring, Tagor Malem

“…To partly solve the global and regional shortages of Mo-99/Tc-99m supply, a conceptual design of a homogeneous solution reactor for Mo-99/Tc-99m medical…”
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Analysis of OECD/NEA medium 1000 MWth sodium-cooled fast reactor using the Monte Carlo serpent code and ENDF/B-VIII.0 nuclear data library by Al-Hamadi, Fatima I., Khuwaileh, Bassam A., Liem, Peng Hong, Hartanto, Donny

“…This study presents a benchmark evaluation of the new ENDF/B-VIII.0 nuclear data library for the Organization for Economic Co-operation and Development/Nuclear…”
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Analysis of NEA-NSC PWR Uncontrolled Control Rod Withdrawal at Zero Power Benchmark Cases with NODAL3 Code by Sembiring, Tagor Malem, Liem, Peng Hong, Pinem, Surian

“…The in-house coupled neutronic and thermal-hydraulic (N/T-H) code of BATAN (National Nuclear Energy Agency of Indonesia), NODAL3, based on the few-group…”
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Development of new ORIGEN2 data library sets for research reactors with light water cooled oxide and silicide LEU (20w/o) fuels based on JENDL-3.3 nuclear data by Liem, Peng Hong, Sembiring, Tagor Malem

“…•We developed new ORIGEN2 data library sets for research reactors based on JENDL-3.3.•The sets cover oxide and silicide LEU fuels with meat density up to…”
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NODAL3 Sensitivity Analysis for NEACRP 3D LWR Core Transient Benchmark (PWR) by Pinem, Surian, Liem, Peng Hong, Sembiring, Tagor Malem

“…This paper reports the results of sensitivity analysis of the multidimension, multigroup neutron diffusion NODAL3 code for the NEACRP 3D LWR core transient…”
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Neutronics analysis of full MOX BWR core simulation experiments - FUBILA: Part 2 by Yamamoto, Toru, Sakai, Tomohiro, Ando, Yoshihira, Liem, Peng Hong, Kikuchi, Shigeto

“…A part of the experimental program FUBILA was dedicated to the study of core physics characteristics of full MOX BWR cores by testing five experimental cores:…”
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Design of transition cores of RSG GAS (MPR-30) with higher loading silicide fuel by Liem, Peng Hong, Sembiring, Tagor Malem

“…A procedure of designing transition cores to achieve the equilibrium silicide core of RSG GAS with higher fuel loading of 300 g U/fuel element (FE) (meat…”
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The Verification of Coupled Neutronics Thermal-Hydraulics Code NODAL3 in the PWR Rod Ejection Benchmark by Pinem, Surian, Liem, Peng Hong, Sembiring, Tagor Malem

“…A coupled neutronics thermal-hydraulics code NODAL3 has been developed based on the few-group neutron diffusion equation in 3-dimensional geometry for typical…”
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JENDL-5.0 nuclear data sensitivity, uncertainty, and similarity analyses on the criticality of RSG GAS multipurpose research reactor by Liem, Peng Hong, Hartanto, Donny

“…•JENDL-5 criticality, S/U, and similarity analysis for RSG GAS first criticality.•Sensitivity coefficients generated by the KSEN option of MCNP6.2.•JENDL-5 new…”
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Small high temperature gas-cooled reactors with innovative nuclear burning by Liem, Peng Hong, Ismail, Sekimoto, Hiroshi

“…Since the innovative concept of CANDLE ( Constant Axial shape of Neutron Flux, nuclide densities and power shape During Life of Energy producing reactor)…”
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Verification of NODAL3 code with PWR MOX/UO2 core transient benchmark by Pinem, Surian, Luthfi, Wahid, Liem, Peng Hong

“…•The in-house code was developed as part of the capacity building in a research institute.•Reactor benchmark data could be used to determine the in-house code…”
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