has been cited by the following article(s):
[1]
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The effect of new library cross-section on fuel using gadolinium burnable poison
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AIP Conference Proceedings,
2024 |
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[2]
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Analysis of the advanced PWR cell MOX fuel using SiC, Zr, FeCrAl, and SS-310 as cladding materials
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AIP Conference Proceedings,
2024 |
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[3]
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Tri Dasa Mega
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2022 |
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[4]
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Simulation of Zircaloy and SiC cladding thermal performance of a nuclear fuel rod subassembly
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Engineering Research …,
2022 |
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[5]
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NEUTRONIC ANALYSIS OF THE VVER-1200 LATTICE CELL FUEL USING WIMSD-5B CODE
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… NUKLIR TRI DASA …,
2022 |
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[6]
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Analysis of LOCA in Cold Leg and Risk Evaluation of Pressurized Water Reactor based NPP
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International Conference on Mechanical,Industrial,Energy and Engineering,
2022 |
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[7]
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ANALYSIS OF THORIUM PIN CELL BURN UP OF THE PWR USING WIMS CODE
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Jurnal Teknologi Reaktor …,
2022 |
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[8]
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Neutronic calculation for PWR MOX fuel pin cells with WIMSD-5B code
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Urania: Jurnal Ilmiah Daur …,
2022 |
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[9]
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Analysis of fuel temperature reactivity coefficient of the PWR using WIMS code
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… REAKTOR NUKLIR TRI …,
2022 |
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[10]
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Heat Transfer Enhancement in Subchannel Geometry of Pressurized Water Reactor Using Water-Based Yttrium Oxide Nanofluid
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2021 |
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[11]
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Analysis of Thermal Hydraulics Behavior of Coolant through a Sub Channel in Fuel Assembly of a Pressurized Water Reactor (PWR)
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2020 |
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[1]
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The effect of new library cross-section on fuel using gadolinium burnable poison
INTERNATIONAL CONFERENCE ON NUCLEAR SCIENCE, TECHNOLOGY, AND APPLICATIONS – ICONSTA 2022,
2024
DOI:10.1063/5.0193396
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[2]
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Analysis of the advanced PWR cell MOX fuel using SiC, Zr, FeCrAl, and SS-310 as cladding materials
INTERNATIONAL CONFERENCE ON NUCLEAR SCIENCE, TECHNOLOGY, AND APPLICATIONS – ICONSTA 2022,
2024
DOI:10.1063/5.0193129
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[3]
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Simulation of Zircaloy and SiC cladding thermal performance of a nuclear fuel rod subassembly
Engineering Research Express,
2022
DOI:10.1088/2631-8695/ac6652
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