Development of nodal diffusion code RAST-V for Vodo–Vodyanoi Energetichesky reactor analysis
Nuclear Engineering and Technology, 2022 This paper presents the development of a nodal diffusion code, RAST-V, and its verification and validation for VVER (vodo–vodyanoi energetichesky reactor) analysis.
Jaerim Jang +2 more
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Neutronic simulation of the CEFR experiments with the nodal diffusion code system RAST-F
Nuclear Engineering and Technology, 2022 CEFR is a small core-size sodium-cooled fast reactor (SFR) using high enrichment fuel with stainless-steel reflectors, which brings a significant challenge to the deterministic methodologies due to the strong spectral effect.
Tuan Quoc Tran, Deokjung Lee
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RAST-K v2—Three-Dimensional Nodal Diffusion Code for Pressurized Water Reactor Core Analysis
Energies, 2020 The RAST-K v2, a novel nodal diffusion code, was developed at the Ulsan National Institute of Science and Technology (UNIST) for designing the cores of pressurized water reactors (PWR) and performing analyses with high accuracy and computational ...
Jinsu Park +7 more
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Nuclear Engineering and TechnologyThis study presents the uncertainty quantification results of steady-state depletion simulations using a multi-physics coupling framework based on the nodal diffusion code RAST-K. Developed for the analysis and optimization of pressurized water reactors,
Jinsu Park, Yeongseok Kang, Deokjung Lee
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MACROSCOPIC CROSS SECTIONS GENERATION BY MONTE CARLO CODE MCS FOR FAST REACTOR ANALYSIS [PDF]
EPJ Web of Conferences, 2021 Recent researches have become more interested in the feasibility of using Monte Carlo (MC) code to generate multi-group (MG) cross sections (XSs) for fast reactor analysis using nodal diffusion codes.
Nguyen Tung Dong Cao +5 more
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IMPLEMENTATION AND COMPARISON OF LATTICE MODULE AND DISCONTINUITY FACTORS MODULE IN PROTEUS TOOLSETS [PDF]
EPJ Web of Conferences, 2021 State-of-the-art core nodal diffusion calculation involves the use of assembly discontinuity factor (ADF) to improve computational accuracy by introducing degree of freedom describing the relationship between interfacial discontinuities in nodal ...
Ni Kan, Hou Jason, Avramova Maria
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COMPARISONS AMONG THREE COUPLING FORMS OF CYLINDRICAL NODAL EXPANSION METHODS [PDF]
EPJ Web of Conferences, 2021 Nodal expansion method (NEM) is a typical nodal method in solving neutron diffusion equation in coarse mesh spatial discretization. NEM has been extended to cylindrical geometry in previous studies.
Wen Yutong, She Ding, Shi Lei, Zhao Jing
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GENERATION OF NODAL CORE SIMULATOR UTILIZING VERA [PDF]
EPJ Web of Conferences, 2021 Nuclear core simulators based upon few-group nodal diffusion method currently are widely used to predict light water reactor core behavior. Nodal parameters’ input, e.g. cross-sections, discontinuity factors, and pin form factors, are typically generated
Turinsky Paul +3 more
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INTRODUCTION OF OSCAR-4 AT THE HIGH FLUX REACTOR (PETTEN) [PDF]
EPJ Web of Conferences, 2021 Since 2005 the nodal diffusion based code system, OSCAR-3, was used for reactor support calculations of operational cycles of the High Flux Reactor in Petten, The Netherlands.
Erasmus B. +4 more
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Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis
Nuclear Engineering and Technology, 2021 Multigroup cross section (MG XS) generation by the UNIST in-house Monte Carlo (MC) code MCS for fast reactor analysis using nodal diffusion codes is reported.
Tung Dong Cao Nguyen +2 more
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