Search Results - "HA, Pham Nhu Viet"
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Neutronics study on small power ADS loaded with recycled inert matrix fuel for transuranic elements transmutation using Serpent code
Published in Nuclear engineering and technology (2021)“…A small power ADS design using thorium oxide and diluent matrix reprocessed fuel is proposed for a high transmutation rate, small reactivity swing, and strong…”
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Assessment of ex-core neutron detectors in prototype Gen-IV sodium-cooled fast reactor (PGSFR)
Published in Annals of nuclear energy (01-04-2019)“…•Assessment of detectors’ locations and number of detectors in PGSFR.•Generation of spatial weighting function using forward fixed-source calculation in…”
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Neutronics study on small power ADS loaded with recycled inert matrix fuel for transuranic elements transmutation using Serpent code
Published in Nuclear engineering and technology (01-07-2021)“…A small power ADS design using thorium oxide and diluent matrix reprocessed fuel is proposed for a high transmutation rate, small reactivity swing, and strong…”
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Investigation of the VVER-1000 reactor pressure vessel neutron fluence and displacement per atom using MCNP6
Published in Radiation physics and chemistry (Oxford, England : 1993) (01-12-2020)“…Ensuring the integrity of the reactor pressure vessel (RPV) during the operating life of nuclear reactors is of paramount importance, and hence the harmful…”
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Evolutionary simulated annealing for fuel loading optimization of VVER-1000 reactor
Published in Annals of nuclear energy (01-02-2021)“…•ESA method was developed to improve original SA by using crossover and mutation operators.•Numerical calculations were performed based on a VVER-1000 MOX core…”
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Dynamic rod worth simulation study for a sodium-cooled TRU burner
Published in Nuclear engineering and design (15-12-2015)“…•Dynamic rod worth calculation methodology for a sodium-cooled TRU burner was developed.•The spatial weighting functions were relatively insensitive to control…”
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Development of EASYQAD Version β: A Visualization Code System for Gamma and Neutron Shielding Calculations
Published in Journal of nuclear science and technology (01-06-2008)“…EASYQAD version β was developed by MATLAB GUI (Graphical User Interface) as a visualization code system based on QAD-CGGP-A point-kernel code for convenient…”
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Development of a PARCS/Serpent model for neutronics analysis of the Dalat nuclear research reactor
Published in Nuclear science and techniques (01-02-2021)“…Cross-sectional homogenization for full-core calculations of small and complex reactor configurations, such as research reactors, has been recently recognized…”
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Study on Transmutation of Minor Actinides as Burnable Poison in VVER-1000 Fuel Assembly
Published in Science and technology of nuclear installations (2019)“…Thermal reactors have been considered as interim solution for transmutation of minor actinides recycled from spent nuclear fuel. Various studies have been…”
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Numerical Investigation of Dynamic Fluctuations Following Nuclear Reactor Transients Using a Simplified Stochastic Model
Published in Journal of nuclear science and technology (01-02-2011)“…In previous studies, a simplified stochastic model (called the stochastic space-dependent kinetics model, SSKM) based on the forward stochastic model in the…”
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Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5
Published in Science and technology of nuclear installations (01-01-2017)“…Neutronics analysis has been performed for the 500 kW Dalat Nuclear Research Reactor loaded with highly enriched uranium fuel using the SRAC code system. The…”
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A Stochastic Approach to Monoenergetic Space-Time Nuclear Reactor Kinetics
Published in Journal of nuclear science and technology (01-08-2010)“…A simplified stochastic model based on the forward stochastic model in the stochastic kinetics theory and the Itô stochastic differential equations is newly…”
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Sensitivity and uncertainty analysis of neutronic and kinetic parameters for CERCER and CERMET fueled ADS using SERPENT 2 and ENDF/B-VIII.0
Published in Annals of nuclear energy (01-04-2022)“…•Sensitivity/Uncertainty analysis using SERPENT 2 and ENDF/B-VIII.0.•Error of keff of CERCER core was significant and larger than that of CERMET…”
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An improved analysis of the OECD/NRC PWR MOX/UO2 core transient benchmark with PARCS/Serpent
Published in Annals of nuclear energy (01-04-2022)“…•Improved solution of the OECD/NRC PWR MOX/UO2 core transient benchmark was obtained with PARCS/Serpent.•Impacts of different diffusion coefficients, radial…”
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A Stochastic Approach to Monoenergetic Space-Time Nuclear Reactor Kinetics
Published in Journal of nuclear science and technology (01-08-2010)“…A simplified stochastic model based on the forward stochastic model in the stochastic kinetics theory and the Itô stochastic differential equations is newly…”
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Journal Article -
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Numerical Investigation of Dynamic Fluctuations Following Nuclear Reactor Transients Using a Simplified Stochastic Model
Published in Journal of nuclear science and technology (01-02-2011)“…In previous studies, a simplified stochastic model (called the stochastic space-dependent kinetics model, SSKM) based on the forward stochastic model in the…”
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Journal Article