Search Results - "Nhu Viet Ha, Pham"

Assessment of ex-core neutron detectors in prototype Gen-IV sodium-cooled fast reactor (PGSFR) by Hartanto, Donny, Lee, Min Jae, Pham, Nhu Viet Ha, Lim, Jae-Yong

“…•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 by Vu, Thanh Mai, Hartanto, Donny, Viet Ha, Pham Nhu

“…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 by Tiep, Nguyen Huu, Hoang, Sy Minh Tuan, Hartanto, Donny, Kim, Kyung Doo, Kim, Jong Kyung, Tuan, Nguyen Minh, Ha, Pham Nhu Viet

“…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 by Tran, Viet-Phu, Phan, Giang T.T., Hoang, Van-Khanh, Ha, Pham Nhu Viet, Yamamoto, Akio, Tran, Hoai-Nam

“…•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 by Kim, Sang Ji, Ha, Pham Nhu Viet, Lee, Min Jae, Kang, Chang Mu

“…•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 by Kim, Jae Cheon, Lee, Hwan Soo, Kim, Soon Young, Nhu Viet Ha, Pham, Kim, Jong Kyung

“…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 by Tran, Viet-Phu, Nguyen, Kien-Cuong, Hartanto, Donny, Tran, Hoai-Nam, Tran, Vinh Thanh, Hoang, Van-Khanh, Ha, Pham Nhu Viet

“…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 by Hoang, Van-Khanh, Nguyen, Huu Tiep, Tran, Hoai-Nam, Tran, Vinh Thanh, Ha, Pham Nhu Viet

“…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 by HA, Pham Nhu Viet, KIM, Jong Kyung

“…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 by Kiet, Hoang Anh Tuan, Hoang, Van-Khanh, Tran, Viet-Phu, Nguyen, Kien-Cuong, Tran, Hoai-Nam, Phan, Giang, Ha, Pham Nhu Viet

“…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 by HA, Pham Nhu Viet, KIM, Jong Kyung

“…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 by Vu, Thanh Mai, Hartanto, Donny, Chu, Thoi Nam, Pham, Nhu Viet Ha, Bui, Thi Hong

“…•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 by Ha, Pham Nhu Viet, Hartanto, Donny, Vu, Thanh Mai, Tran, Vinh Thanh, Tran, Viet-Phu

“…•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 by HA, Pham Nhu Viet, KIM, Jong Kyung

“…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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Numerical Investigation of Dynamic Fluctuations Following Nuclear Reactor Transients Using a Simplified Stochastic Model by HA, Pham Nhu Viet, KIM, Jong Kyung

“…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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