Results 11 to 20 of about 2,702 (149)
Verification of a two-step code system MCS/RAST-F to fast reactor core analysis
Nuclear Engineering and Technology, 2022 RAST-F is a new full-core analysis code based on the two-step approach that couples a multi-group cross-section generation Monte-Carlo code MCS and a multi-group nodal diffusion solver.
Tuan Quoc Tran +3 more
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New 3D Diffusion Code Based on The Nodal Polynomial Expansion
Brazilian Journal of Radiation Sciences, 2021 Nodal Expansion Method (NEM) is widely employed in the neutronic design of nuclear reactors core. The main reason is its higher computational performance and efficiency when compared with the conventional fine mesh difference method or finite element ...
Jadna Mara Santos Mendes +2 more
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DEVELOPMENT AND VERIFICATION OF T-TRACE/PANTHER COUPLED CODE [PDF]
EPJ Web of Conferences, 2021 Multi-physics coupled simulations have become increasingly important during the last two decades being one of the major field of application in the nuclear technology.
Abarca A. +5 more
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CEFR control rod drop transient simulation using RAST-F code system
Nuclear Engineering and Technology, 2023 This study aimed to verify and validate the transient simulation capability of the hybrid code system RAST-F for fast reactor analysis. For this purpose, control rod (CR) drop experiments involving eight separate CRs and six CR groups in the China ...
Tuan Quoc Tran +3 more
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Atom Indonesia, 2021 Diffusion approximation is an important approximation used to model a nuclear reactor core with a quite good accuracy and less computational cost. This approximation has been used widely around the globe for various kinds of nuclear reactors.
H. Ardiansyah, M. R. Oktavian
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Nuclear Engineering and Technology, 2022 The United Arab Emirates is currently building and operating four units of the APR-1400 developed by a South Korean vendor, Korea Electric Power Corporation (KEPCO).
Jwaher Alnaqbi +4 more
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HEXAGONAL PWR-CORE MODELING AND SIMULATION WITH APPLICATION OF NECP-BAMBOO [PDF]
EPJ Web of Conferences, 2021 In this paper, the modeling and simulation of the PWRs loaded with hexagonal fuel assemblies has been implemented with the NECP-Bamboo code. NECP-Bamboo, consisting of a 2D lattice code named Bamboo-Lattice and a 3D steady-state core code named Bamboo ...
Zhang Cheng +3 more
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Journal of Nuclear Engineering, 2022 A new module for the AZtlan Nodal HEXagonal (AZNHEX) code, which is part of the AZTLAN Platform, was recently developed based on the Simplified Spherical Harmonics (SPL) scheme to deal with the challenges presented in small fast reactor cores, such as ...
Guillermo Muñoz-Peña +4 more
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ANALYSIS OF THE OECD/NEA SFR BENCHMARK WITH ANTS REDUCED-ORDER NODAL DIFFUSION SOLVER AND THE SERPENT MONTE CARLO CODE [PDF]
EPJ Web of Conferences, 2021 In order to meet modern industrial and scientific demands the Kraken multi-physics platform’s development was recently launched at VTT Technical Research Centre of Finland.
Szogradi Marton
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Coupled neutronics/thermal-hydraulic analysis of ANTS-100e using MCS/RAST-F two-step code system
Nuclear Engineering and Technology, 2023 The feasibility of using the Monte Carlo code MCS to generate multigroup cross sections for nodal diffusion simulations RAST-F of liquid metal fast reactors is investigated in this paper.
Tung Dong Cao Nguyen +2 more
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