Search Results - "Pinem, Surian"

Effect of cross-sections data on calculated static neutronic parameters of PWR MOX/UO2 core transient benchmark case using NODAL3 code by Wahid Luthfi, Surian Pinem

“…This paper describes the effect of cross-section data generated by several codes on calculated neutronic parameters. The Pressurized Water Reactor Mixed Oxide…”
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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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Transient calculation on TRIGA 2000 of plate-type fuel element using RELAP5, EUREKA2/RR, and MTR-DYN codes by Dibyo, Sukmanto, Pinem, Surian, Widodo, Surip

“…The TRIGA 2000 reactor Bandung is proposed to convert from rod-type fuel to plate-type fuel because there are no manufacturers in the world that still produce…”
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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 by Pinem, Surian, Dibyo, Sukmanto, Luthfi, Wahid, Wardhani, Veronica Indriati Sri, Hartanto, Donny

“…Steady-state and transient analysis of reactor core under Reactivity-Initiated Accident (RIA) conditions are important for reactor operation safety. The…”
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CFD simulation of partial channel blockage on plate-type fuel of TRIGA-2000 conversion reactor core by Sukmanto Dibyo, Wahid Luthfi, Surian Pinem, Ign Djoko Irianto, Veronica Indriati Sriwardhani

“…A nuclear reactor cooling system that has been operating for a long time can carry some debris into a fuel coolant channel, which can result in a blockage. An…”
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Reactivity insertion accident analysis during uranium foil target irradiation in the RSG-GAS reactor core by Pinem, Surian, Sembiring, Tagor, Surbakti, Tukiran

“…Analysis of the steady-state and reactivity insertion accident is very important for the safety of reactor operations. In this study, steady-state and…”
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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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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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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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VALIDATION OF SRAC CODE SYSTEM FOR NEUTRONIC PARAMETERS CALCULATION OF THE PWR MOX/UO2 CORE BENCHMARK by Luthfi, Wahid, Pinem, Surian

“…VALIDATION OF SRAC CODE SYSTEM FOR NEUTRONIC PARAMETERS CALCULATION OF THE PWR MOX/UO2 CORE BENCHMARK. Determination of neutronic parameter value is an…”
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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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CFD simulation on sub-channel blockage in the fuel plate of RSG-GAS reactor by Dibyo, Sukmanto, Pinem, Surian, Sulistyo, Farisy Yogatama, Sriwardhani, Veronica Indriati

“…The main objective of the paper is to simulate flow blockage in the sub-channel fuel plate in the Indonesian RSG-GAS research reactor. Utilizing SolidWorks CFD…”
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NEUTRONIC AND THERMAL HYDRAULICS ANALYSIS OF CONTROL ROD EFFECT ON THE OPERATION SAFETY OF TRIGA 2000 REACTOR by Pinem, Surian, Surbakti, Tukiran, Kuntoro, Iman

“…NEUTRONIC AND THERMAL HYDRAULICS ANALYSIS OF CONTROL ROD EFFECT ON THE OPERATION SAFETY OF TRIGA 2000 REACTOR. Analysis of neutronic and thermal-hydraulics…”
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Control rods’ position history effect on the Indonesian multipurpose research reactor RSG-GAS operation and safety parameters by Pinem, Surian, Luthfi, Wahid, Hartanto, Donny, Liem, Peng Hong

“…The present work extends the analysis of the first working core of RSG-GAS to the burnup calculation. During the fuel management calculations of RSG-GAS, the…”
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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 by Sembiring, Tagor Malem, Pinem, Surian, Hartanto, Donny, Liem, Peng Hong

“…•A continuation work to confirm the RSG-GAS equilibrium silicide core parameters.•Core parameters include excess reactivity and integral & total control rod…”
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Burnup determination of Full-Scale, High-Density U3Si2-Al (4.8 gU/cc) fuel plate using destructive radiochemical technique by Br. Ginting, Aslina, Yanlinastuti, Boybul, Supardjo, Sungkono, Pinem, Surian, Carlos Sihotang, Juan

“…•Zeolite effectively absorbs Cs-137 and Cs-134 isotopes from U3Si2/Al fuel solution in the cation–anion exchange method.•In radiochemical analysismethod, using…”
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Neutronic Analysis of the AP1000 Fuel Assembly with Accident Tolerant Cladding Materials by Luthfı, Wahid, Pinem, Surian, Sulistyo, Farisy Yogatama, Surbakti, Tukiran

“…An alternative material for fuel cladding was required to prevent oxidation caused by interacting with steam, leading to improvement in core integrity. This…”
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ANALYSIS OF UNCONTROLLED REACTIVITY INSERTION TRANSIENT OF TRIGA MARK 2000 BANDUNG USING MTR PLATE TYPE FUEL ELEMENT by Pinem, Surian, Surbakti, Tukiran, Kuntoro, Imam

“…ANALYSIS OF UNCONTROLLED REACTIVITY INSERTION TRANSIENT OF TRIGA MARK 2000 BANDUNG USING MTR PLATE TYPE FUEL ELEMENT. Analysis of uncontrolled reactivity…”
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Fuel element burnup measurements for the equilibrium LEU silicide RSG GAS (MPR-30) core under a new fuel management strategy by Pinem, Surian, Liem, Peng Hong, Sembiring, Tagor Malem, Surbakti, Tukiran

“…•Burnup measurement of fuel elements comprising the new equilibrium LEU silicide core of RSG GAS.•The burnup measurement method is based on a linear…”
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Core Design TRIGA2000 Bandung Using U3Si2Al Fuel Element MTR Type by Pinem, Surian, Surbakti, Tukiran, Sembiring, Tagor M.

“…DESAIN TERAS REAKTOR TRIGA2000 BANDUNG MENGGUNAKAN TIPE ELEMEN BAKAR MTR U3Si2/Al. Reaktor TRIGA2000 Bandung selama ini menggunakan bahan bakar jenis silinder…”
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