Results 21 to 30 of about 30,351 (207)
Explicit decay heat calculation in the nodal diffusion code DYN3D [PDF]
Annals of Nuclear Energy, 2018 The residual radioactive decay heat plays an important role in some accident scenarios and, therefore, needs to be accurately calculated when performing accident analyses. The current reactor simulation codes used for accident analysis account for the residual decay heat by means of simplified models.
Bilodid, Y. +3 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
doaj +1 more source
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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Three-dimensional multigroup diffusion code ANDEX based on nodal method for cartesian geometry. [PDF]
Journal of Nuclear Science and Technology, 1990 An analytic polynomial nodal method using partial currents has been derived for the solution of multigroup neutron diffusion equations in three-dimensional (3-D) cartesian geometry. This method is characterized by expressing the source and leakage terms in an auxiliary 1-D diffusion equation by quadratic polynomials and solving it analytically.
Noboru ITO, Toshikazu TAKEDA
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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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Transport Corrections in Nodal Diffusion Codes for HTR Modeling [PDF]
, 2010 The cores and reflectors of High Temperature Reactors (HTRs) of the Next Generation Nuclear Plant (NGNP) type are dominantly diffusive media from the point of view of behavior of the neutrons and their migration between the various structures of the reactor.
Ougouag, Abderrafi M. +1 more
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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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