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Kien Cuong Nguyen

Observed name: Kien-Cuong Nguyen
ORCID: 0000-0002-1263-7995
Observed ORCIDs: 0000-0002-1263-7995, 0000-0002-5151-5157
OpenAlex ID: A5034527210
Criticality and rod worth analysis of the DNRR research reactor using the SRAC and MCNP5 codes
2019 · Quang Binh Do, Giang T.T. Phan, et al. · Nuclear Engineering and Design · 24
Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5
2017 · Giang Phan, Hoai-Nam Tran, et al. · Science and Technology of Nuclear Installations · 22
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Development of a PARCS/Serpent model for neutronics analysis of the Dalat nuclear research reactor
2021 · Viet-Phu Tran, Kien-Cuong Nguyen, et al. · Nuclear Science and Techniques · 17
Nuclide Identification Algorithm for the Large-Size Plastic Detectors Based on Artificial Neural Network
2022 · Cao Van Hiep, Dinh Tien Hung, et al. · IEEE Transactions on Nuclear Science · 15
Conceptual Design of a 10 MW Multipurpose Research Reactor Using VVR-KN Fuel
2020 · Nhi-Dien Nguyen, Kien-Cuong Nguyen, et al. · Science and Technology of Nuclear Installations · 14
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Design Analyses for Full Core Conversion of The Dalat Nuclear Research Reactor
2014 · Ba Vien Luong, Vinh Vinh Le, et al. · Nuclear Science and Technology · 8
Steady-State Thermal-Hydraulic Analysis of the LEU-Fueled Dalat Nuclear Research Reactor
2021 · Kien-Cuong Nguyen, Vinh-Vinh Le, et al. · Science and Technology of Nuclear Installations · 6
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Criticality and sensitivity/uncertainty analysis of the DNRR with LEU fuel using MCNP6.3 and the latest data libraries
2025 · Duc-Tu Dau, Nhi-Dien Nguyen, et al. · Nuclear Engineering and Design · 5
Interim Storage of the Dalat Nuclear Research Reactor: Radiation Safety Analysis
2020 · Kien-Cuong Nguyen, Vinh-Vinh Le, et al. · Science and Technology of Nuclear Installations · 5
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Kinetic parameters of the Dalat nuclear research reactor with LEU fuel using MCNP6 and JENDL-5 library
2025 · Duc-Tu Dau, Nhi-Dien Nguyen, et al. · Nuclear Technology and Radiation Protection · 4
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Some Main Results of Commissioning of The Dalat Research Reactor with Low Enriched Fuel
2014 · Nhi Dien Nguyen, Ba Vien Luong, et al. · Nuclear Science and Technology · 3
Evaluation of neutron flux distribution in structural components and activation products in aluminum alloy at 13-2 channel of the DNRR
2021 · Quoc Duong Tran, Nhi Dien Nguyen, et al. · Nuclear Science and Technology · 1
Reactivity induced transient analysis when the occurrence of leakage in the dry irradiation channels of the Dalat Nuclear Research Reactor
2018 · Duc Tu Dau, Minh Tuan Nguyen, et al. · Nuclear Science and Technology · 1
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Comparing ASEAN nuclear research reactor operating cultures for supporting multinational human reliability analysis
2026 · Wasin Vechgama, Jinkyun Park, et al. · Progress in Nuclear Energy
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Development of a Compact Digital Multichannel Analyzer based on FPGA
2024 · Hoai Phuong Pham, Nhi Dien Nguyen, et al. · Nuclear Science and Technology
Determination of the Activity Inventory in the Structural Components of the Dalat Nuclear Research Reactor for Its Decommissioning Planning
2022 · Quoc-Duong Tran, Kien-Cuong Nguyen, et al. · Science and Technology of Nuclear Installations
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Calculation of critical core configurations of a research reactor using MTR, IRT-4M, VVR-KN fuel assemblies
2018 · Quoc Duong Tran, Nhi Dien Nguyen, et al. · Nuclear Science and Technology
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Thermal-hydraulics analysis for VVR-KN fuel lead test using PLTEMP code
2018 · Nguyen Thanh Vinh Ho, Vinh Vinh Le, et al. · Nuclear Science and Technology
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Validation of neutronics libraries through benchmarks and critical configurations of The Dalat Nuclear Research Reactor using low enriched uranium fuel by monte carlo method
2013 · Kien Cuong Nguyen, Ton Nghiem Huynh, et al. · Nuclear Science and Technology
Preliminary study on new configuration with LEU fuel assemblies for the Dalat nuclear research reactor
2008 · Van Lam Pham, Vinh Vinh Le, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Search for $alpha$-emission in the decay of spontaneously fissionable isomers
1973 · A. G. Belov, Yu.P. Gangrskii, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
PRODUCTION OF SPONTANEOUSLY FISSIBLE ISOMER $sup 242$Am AT THERMAL NEUTRON CAPTURE.
1969 · Yu.P. Gangrskii, K.A. Gavrilov, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Works count: 22
Citation count: 125
H-index: 6
I10-index: 5
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