Thermal, structural and optical properties of TeO2–Na2O–TiO2 glassy system
Sign Up to like & getrecommendations! Published in 2019 at "Journal of Materials Science: Materials in Electronics"
DOI: 10.1007/s10854-019-01496-6
Abstract: In this work, 80TeO2–(20 − x) Na2O–xTiO2 (x = 0, 5, 10 and 20) mol% glasses by melting quenching technique were obtained. Density (ρ) and molar volume (Vm) of these glasses have been investigated. The characterization was performed by… read more here.
Keywords: tio2; thermal structural; glassy system; optical properties ... See more keywords
Improved numerical algorithm and experimental validation of a system thermal-hydraulic/CFD coupling method for multi-scale transient simulations of pool-type reactors
Sign Up to like & getrecommendations! Published in 2017 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2017.01.002
Abstract: Abstract The paper describes the development and validation of a coupling methodology between the best-estimate system thermal-hydraulic code RELAP5-3D and the CFD code FLUENT, conceived for high fidelity plant-scale safety analyses of pool-type reactors. The… read more here.
Keywords: methodology; validation; pool type; thermal hydraulic ... See more keywords
Coupled system thermal Hydraulics/CFD models: General guidelines and applications to heavy liquid metals
Sign Up to like & getrecommendations! Published in 2021 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2020.107990
Abstract: Abstract This work aims to review the general guidelines to be adopted to perform coupled System Thermal Hydraulics (STH)/CFD calculations. The coupled analysis is often required when complex phenomena characterized by different characteristic time and… read more here.
Keywords: sth cfd; applications heavy; thermal hydraulics; general guidelines ... See more keywords
Lead coolant modeling in system thermal-hydraulic code HYDRA-IBRAE/LM and some validation results
Sign Up to like & getrecommendations! Published in 2020 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2019.110463
Abstract: Abstract The paper overviews the challenges associated with the development of a system thermal-hydraulic code applied for lead coolant by the example of a Russian system thermal-hydraulic code HYDRA-IBRAE/LM. It presents the PIRT describing relevant… read more here.
Keywords: system thermal; lead coolant; hydraulic code; thermal hydraulic ... See more keywords
A comprehensive survey of inverse uncertainty quantification of physical model parameters in nuclear system thermal–hydraulics codes
Sign Up to like & getrecommendations! Published in 2021 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2021.111460
Abstract: Uncertainty Quantification (UQ) is an essential step in computational model validation because assessment of the model accuracy requires a concrete, quantifiable measure of uncertainty in the model predictions. The concept of UQ in the nuclear… read more here.
Keywords: uncertainty; uncertainty quantification; iuq; model ... See more keywords
System Thermal-hydraulics Model for Fluoride Salt-Cooled Reactor Based On Small Advanced High Temperature Reactor (smAHTR) Design Concept
Sign Up to like & getrecommendations! Published in 2023 at "Journal of Nuclear Engineering and Radiation Science"
DOI: 10.1115/1.4062500
Abstract: A system thermal-hydraulics model for a fluoride-salt-cooled high-temperature reactor (FHR) based on the small modular advanced high-temperature reactor (SmAHTR) design concept is developed, using RELAP5-3D. The SmAHTR components modelled in the simulations include: the reactor… read more here.
Keywords: reactor; system; smahtr; high temperature ... See more keywords