Results 11 to 20 of about 308 (180)

Application of CUPID for subchannel-scale thermal–hydraulic analysis of pressurized water reactor core under single-phase conditions

open access: yesNuclear Engineering and Technology, 2018
There have been recent efforts to establish methods for high-fidelity and multi-physics simulation with coupled thermal–hydraulic (T/H) and neutronics codes for the entire core of a light water reactor under accident conditions. Considering the computing
Seok Jong Yoon   +4 more
doaj   +1 more source

CTF and FLOCAL Thermal Hydraulics Validations and Verifications within a Multiscale and Multiphysics Software Development

open access: yesEnergies, 2021
Simulation codes allow one to reduce the high conservativism in nuclear reactor design improving the reliability and sustainability associated with nuclear power.
Sebastian Davies   +8 more
doaj   +1 more source

MULTI-PHYSICS TRANSIENT SIMULATIONS WITH TRIPOLI-4® [PDF]

open access: yesEPJ Web of Conferences, 2021
In this work, we present the first dynamic calculations performed with the Monte Carlo neutron transport code TRIPOLI-4R with thermal-hydraulics feedback.
Faucher Margaux   +2 more
doaj   +1 more source

Recognition algorithm of non punctured polarization codes based on structural characteristics of coding matrix

open access: yesTongxin xuebao, 2022
In order to solve the problems of complexity and poor error adaptability in the blind recognition of standard non-punctured polarization codes, the theorems and propositions that could characterize the relationship between the code length and code rate ...
Yao WANG   +3 more
doaj   +2 more sources

Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes

open access: yesScience and Technology of Nuclear Installations, 2012
In order to assess the accuracy and validity of subchannel, system, and computational fluid dynamics codes, the Paul Scherrer Institut has participated in the OECD/NRC PSBT benchmark with the thermal-hydraulic system code TRACE5.0 developed by US NRC ...
Taewan Kim   +3 more
doaj   +1 more source

MIXED CORE SUBCHANNEL MODEL FOR SUBCAL AND COUPLING WITH ANDREA

open access: yesActa Polytechnica CTU Proceedings, 2018
This paper presents the results of an analysis of flow distribution in VVER-1000 mixed core consisting of fuel assemblies with non-identical spacing grids.
Vojtěch Caha, Jiří Čížek
doaj   +1 more source

High-Fidelity Steady-State and Transient Simulations of an MTR Research Reactor Using Serpent2/Subchanflow

open access: yesEnergies, 2022
In order to join efforts to develop high-fidelity multi-physics tools for research reactor analysis, the KIT is conducting studies to modify the coupled multi-physics codes developed for power reactors.
Juan Carlos Almachi   +2 more
doaj   +1 more source

EFFECT OF ENERGY DEPOSITION MODELLING IN COUPLED STEADY STATE MONTE CARLO NEUTRONICS/THERMAL HYDRAULICS CALCULATIONS [PDF]

open access: yesEPJ Web of Conferences, 2021
In coupled calculations with Monte Carlo neutronics and thermal hydraulics the Monte Carlo code is used to produce a power distribution which in practice means tallying the energy deposition.
Tuominen Riku   +4 more
doaj   +1 more source

DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part I)

open access: yesEnergies, 2021
Understanding and optimizing the relation between nuclear reactor components or physical phenomena allows us to improve the economics and safety of nuclear reactors, deliver new nuclear reactor designs, and educate nuclear staff.
Sebastian Davies   +7 more
doaj   +1 more source

Benchmark of Subchannel Code VIPRE-W with PSBT Void and Temperature Test Data

open access: yesScience and Technology of Nuclear Installations, 2012
This paper summarizes comparisons of VIPRE-W thermal-hydraulic subchannel code predictions with measurements of fluid temperature and void from pressurized water reactor subchannel and bundle tests. Using an existing turbulent mixing model, the empirical
Y. Sung   +5 more
doaj   +1 more source

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