Coupled neutronics/thermal-hydraulics analysis of a full PWR core using RMC and CTF
Sign Up to like & getrecommendations! Published in 2017 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2017.05.041
Abstract: Abstract A hybrid coupled strategy was proposed for a coupled neutronics and thermal-hydraulics analysis of a full PWR core, using the continuous-energy Reactor Monte Carlo code (RMC) and the sub-channel code COBRA-TF (CTF). In the… read more here.
Keywords: ctf; full core; coupled neutronics; neutronics thermal ... See more keywords
Transient analysis of the Brazilian Multipurpose Reactor by the coupled neutronics and thermal hydraulics code NTHC1
Sign Up to like & getrecommendations! Published in 2020 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2020.107449
Abstract: Abstract Dynamical behavior of the Brazilian Multipurpose Reactor (RMB) is investigated by using the coupled neutronics and thermal hydraulics code NTHC1, which consists of the neutron point kinetics (NPK) equations with six groups of delayed… read more here.
Keywords: brazilian multipurpose; multipurpose reactor; coupled neutronics; neutronics thermal ... See more keywords
Rod bundle thermal-hydraulics experiment with water and water-Al2O3 nanofluid for small modular reactor
Sign Up to like & getrecommendations! Published in 2021 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2020.107870
Abstract: Abstract This study offers state-of-the-art rod bundle facility development and testing with modified coolant, with the prospects and challenges for the small modular reactor (SMR). The thermal-hydraulics characteristics of a 3 × 3 square array… read more here.
Keywords: rod bundle; water; modular reactor; thermal hydraulics ... See more keywords
Coupled system thermal Hydraulics/CFD models: General guidelines and applications to heavy liquid metals
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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
Predictive uncertainty reduction in coupled neutron-kinetics/thermal hydraulics modeling of the BWR-TT2 benchmark
Sign Up to like & getrecommendations! Published in 2017 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2016.12.011
Abstract: Abstract By applying a comprehensive predictive modeling methodology, this work demonstrates a substantial (up to 50%) reduction of uncertainties in the predicted total transient power in the BWR Turbine Trip 2 (BWR-TT2) benchmark while calibrating… read more here.
Keywords: tt2 benchmark; methodology; bwr tt2; thermal hydraulics ... See more keywords
Validation of Star-CCM+ for liquid metal thermal-hydraulics using TALL-3D experiment
Sign Up to like & getrecommendations! Published in 2019 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2018.11.015
Abstract: Abstract Computational Fluid Dynamics (CFD) provides means for high-fidelity 3D thermal-hydraulics analysis of Generation IV pool-type nuclear reactors. However, to be used in the decision making process a proof of code adequacy for intended application… read more here.
Keywords: pool; star ccm; validation; thermal hydraulics ... See more keywords
Best Estimate Plus Uncertainty (BEPU): Status and perspectives
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DOI: 10.1016/j.nucengdes.2019.110190
Abstract: Abstract The Best Estimate Plus Uncertainty (BEPU) constitutes an approach, a procedure or a framework aimed at making feasible the application of nuclear thermal-hydraulics to the licensing and the safety evaluation processes of Nuclear Power… read more here.
Keywords: best estimate; plus uncertainty; bepu; uncertainty bepu ... See more keywords
Recent challenges in subchannel thermal-hydraulics-CFD modeling, subchannel analysis, CHF experiments, and CHF prediction
Sign Up to like & getrecommendations! Published in 2019 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2019.110236
Abstract: Abstract Reactor core thermal hydraulics is, or has always been, one of the key components for the safety of nuclear reactor. Continuous efforts have been devoted to the investigation and understanding of its basic physical… read more here.
Keywords: rod bundle; subchannel analysis; chf; thermal hydraulics ... See more keywords
ALFRED: A revised concept to improve pool related thermal-hydraulics
Sign Up to like & getrecommendations! Published in 2019 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2019.110359
Abstract: Abstract ALFRED, namely the Advanced Lead-cooled Fast Reactor European Demonstrator, has been conceived to serve the industrial deployment of the Lead-cooled Fast Reactor (LFR) technology. ALFRED is a demonstrator reactor designed with the specific purpose… read more here.
Keywords: pool; thermal hydraulics; alfred revised; fast reactor ... See more keywords
Mechanistic modeling of the thermal-hydraulics in polydispersed flow film boiling in LOCA conditions
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DOI: 10.1016/j.nucengdes.2019.110388
Abstract: Abstract Much effort has been devoted by the nuclear community to develop mechanistic models to predict the heat dissipation of fuel rods during a loss of coolant accident (LOCA). However, there is still the challenge… read more here.
Keywords: flow film; film boiling; polydispersed flow; thermal hydraulics ... 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