On the prediction of critical heat flux using a physics-informed machine learning-aided framework
The critical heat flux (CHF) corresponding to the departure from nucleate boiling (DNB) crisis
is essential to the design and safety of a two-phase flow boiling system. Despite the …
is essential to the design and safety of a two-phase flow boiling system. Despite the …
[HTML][HTML] Assessment of the state-of-the-art AI methods for critical heat flux prediction
Abstract Critical Heat Flux (CHF) plays a pivotal role in ensuring reliability and safety within
boiling two-phase flow systems. Despite the development of numerous CHF prediction tools …
boiling two-phase flow systems. Despite the development of numerous CHF prediction tools …
Improved departure from nucleate boiling prediction in rod bundles using a physics-informed machine learning-aided framework
The critical heat flux (CHF) corresponding to the departure from nucleate boiling (DNB) crisis
is a regulatory limit for the licensing of pressurized water reactors (PWRs) worldwide …
is a regulatory limit for the licensing of pressurized water reactors (PWRs) worldwide …
40th Anniversary of the first international topical meeting on nuclear reactor thermal-hydraulics: Highlights of thermal-hydraulics research in the past four decades
E Merzari, FB Cheung, SM Bajorek… - Nuclear Engineering and …, 2021 - Elsevier
The year 2020 marks the 40th anniversary of the first International Topical Meeting on
Nuclear Reactor Thermal-hydraulics (NURETH-1). Hosted by the thermal-hydraulics division …
Nuclear Reactor Thermal-hydraulics (NURETH-1). Hosted by the thermal-hydraulics division …
Sensitivity analysis of transient critical heat flux by RIA under high-pressure flow boiling conditions in TRTL
A reactivity-initiated accident (RIA) is a design-basis accident under which critical heat flux
(CHF) is likely to be exceeded. The operational margin for RIAs is currently determined …
(CHF) is likely to be exceeded. The operational margin for RIAs is currently determined …
[PDF][PDF] Machine learning-based critical heat flux predictors in subcooled and low-quality flow boiling
The subcooled and low-quality flow boiling critical heat flux (CHF) corresponding to the
departure from nucleate boiling (DNB) is one of the major limiting factors in the design and …
departure from nucleate boiling (DNB) is one of the major limiting factors in the design and …
Thermal-hydraulic two-phase modeling of reactivity-initiated transients with CATHARE2–Application to SPERT-IV simulation
JM Labit, N Seiler, O Clamens, E Merle - Nuclear Engineering and Design, 2021 - Elsevier
Abstract Reactivity-Initiated Accidents (RIA) in nuclear reactor cores are very complex
multiphysic transients. They consist in a very fast power excursion in the core, leading to wall …
multiphysic transients. They consist in a very fast power excursion in the core, leading to wall …
Experimental investigation of power transient flow boiling
To advance the mechanistic understanding of power transients in flow boiling, experimental
investigations are performed to capture the thermal response of four different kinds of …
investigations are performed to capture the thermal response of four different kinds of …
Recently revisited TH issues and associated R&D A French perspective
P Ruyer - Nuclear Engineering and Design, 2023 - Elsevier
This paper presents an overview of some recent evolutions in the field of thermal-hydraulics
(TH) within nuclear safety studies in France, therefore restricted to Pressurized Water …
(TH) within nuclear safety studies in France, therefore restricted to Pressurized Water …
Hybrid improved empirical mode decomposition and artificial neural network model for the prediction of Critical Heat Flux (CHF)
Three Hybrid artificial neural network (ANN) models namely radial basis function (RBF),
generalized regression neural networks (GRNN), and multi-layer perceptron (MLP) …
generalized regression neural networks (GRNN), and multi-layer perceptron (MLP) …