Neural-based time series forecasting of loss of coolant accidents in nuclear power plants

MI Radaideh, C Pigg, T Kozlowski, Y Deng… - Expert Systems with …, 2020 - Elsevier
In the last few years, deep learning in neural networks demonstrated impressive successes
in the areas of computer vision, speech and image recognition, text generation, and many …

Safety assessment of AP1000: Common transients, analysis codes and research gaps

SA Olatubosun, A Ayodeji, MA Amidu - Nuclear Engineering and Design, 2021 - Elsevier
The commercial operation of the AP1000 in China's Sanmen nuclear power plant
demonstrates the feasibility of reactors with advanced passive safety systems. However …

A review of neutronics and thermal hydraulics–based screening methods applied to accelerated nuclear fuel qualification

JP Gorton, CM Petrie, AT Nelson - Progress in Nuclear Energy, 2023 - Elsevier
This paper reviews the state-of-the-art engineering approach for using thermal hydraulic
(TH) and neutronics modeling and simulation (M&S) tools to perform rapid screening studies …

[HTML][HTML] Demonstration of the E-BEPU methodology for SL-LOCA in a Gen-III PWR reactor

P Mazgaj, P Darnowski, A Kaszko, J Hortal… - Reliability Engineering & …, 2022 - Elsevier
The paper presents the first practical application of the alternative Extended Best Estimate
Plus Uncertainty (E-BEPU) methodology. The E-BEPU is the systematic risk-informed …

[HTML][HTML] Using machine learning to forecast and assess the uncertainty in the response of a typical PWR undergoing a steam generator tube rupture accident

TCH Nguyen, A Diab - Nuclear Engineering and Technology, 2023 - Elsevier
In this work, a multivariate time-series machine learning meta-model is developed to predict
the transient response of a typical nuclear power plant (NPP) undergoing a steam generator …

Using machine learning to predict the fuel peak cladding temperature for a large break loss of coolant accident

W Sallehhudin, A Diab - Frontiers in Energy Research, 2021 - frontiersin.org
In this paper the use of machine learning (ML) is explored as an efficient tool for uncertainty
quantification. A machine learning algorithm is developed to predict the peak cladding …

Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 3: Thermal hydraulic evaluation of large break LOCA under high-burnup …

A Wysocki, J Hirschhorn, I Greenquist, N Capps - Annals of Nuclear Energy, 2023 - Elsevier
Increasing the peak rod average burnup of pressurized water reactor (PWR) fuel beyond 62
GWd/tU may increase fuel fragmentation, relocation, and dispersal (FFRD) susceptibility …

Integrated framework for model assessment and advanced uncertainty quantification of nuclear computer codes under bayesian statistics

MI Radaideh, K Borowiec, T Kozlowski - Reliability Engineering & System …, 2019 - Elsevier
A framework for model evaluation and uncertainty quantification (UQ) is presented with
applications oriented to nuclear engineering simulation codes. Our framework is inspired by …

A comprehensive Bayesian framework for the development, validation and uncertainty quantification of thermal-hydraulic models

R Cocci, G Damblin, A Ghione, L Sargentini… - Annals of Nuclear …, 2022 - Elsevier
The development, validation and uncertainty quantification of closure laws used into thermal–
hydraulic system codes is a key issue before applying the BEPU (Best Estimate Plus …

The large-break LOCA uncertainty analysis in a VVER-1000 reactor using TRACE and DAKOTA

O Safarzadeh, A Pourrostam - Nuclear Engineering and Design, 2023 - Elsevier
An uncertainty analysis is inevitable in simulating reactor performance, particularly in the
accident analysis for the estimation of safety borders. In this paper, the application of the …