ANS / Publications / Journals / Nuclear Technology

Uncertainty and Sensitivity Analyses for Postulated Severe Accidents of Reference PWRs and SMRs in the Frame of the IAEA CRP and Relevant Insights

Kwang-Il Ahn, Federico Mezio, Shaukat Ali, Xuewu Cao, Yong Jin Cho, Bassam Khuwaileh, Victor Martinez-Quiroga, Fulvio Mascari, Fabrizio Gabrielli, David Luxat, Tatjana Jevremovic

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 1879-1905

Research Article / dx.doi.org/10.1080/00295450.2024.2422260

Adaptive Sampling Limit Surface Search Application to Identify Cliff-Edge Effects in Severe Accident Uncertainty Analysis

Pietro Maccari, Andrea Bersano, Fabrizio Gabrielli, Fulvio Mascari

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 1906-1920

Research Article / dx.doi.org/10.1080/00295450.2024.2430128

Applying Shapley Effect for Sensitivity Analysis During Reactor Transient

Basma Foad, Rabab Elzohery, Jeremy Roberts, David R. Novog

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 1921-1936

Research Article / dx.doi.org/10.1080/00295450.2024.2435786

Sensitivity Analysis on the DYNASTY Facility 1D Modelica Models with the DAKOTA-FMU Approach

Gabriele Benzoni, Carolina Introini, Andrea Missaglia, Xiang Wang, Antonio Cammi

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 1937-1959

Research Article / dx.doi.org/10.1080/00295450.2024.2440693

Major Achievements of the EC MUSA Project

L. E. Herranz, S. Beck, V. H. Sánchez-Espinoza, F. Mascari, S. Brumm, O. Coindreau, S. Paci

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 1960-1970

Research Article / dx.doi.org/10.1080/00295450.2024.2444081

Lessons Learned and Best Practices on BWR Severe Accident Uncertainty and Sensitivity Analysis in the Framework of the IAEA CRP I31033

J. Ortiz-Villafuerte, E. K. Boafo, L. Herranz, R. López-Morones, F. Mascari, Tatjana Jevremovic

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 1971-1985

Research Article / dx.doi.org/10.1080/00295450.2025.2468599

Implementation of the SP₃ Solver with Gray Boundary Conditions in OpenFOAM for Thermal Radiation Modeling: Application to Molten Salt Reactors

Mahdi Aghili Nasr, Antonio Cammi, AhmadReza Zolfaghari, Reza Akbari

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 1986-2004

Research Article / dx.doi.org/10.1080/00295450.2025.2470015

Monte Carlo Filtering Technique Applied to Both Quantitative and Qualitative Uncertain Variables in the Sensitivity Analysis of Hydrogen Generation and RPV Failure During a BWR STSBO

Javier Ortiz-Villafuerte, Heriberto Sánchez-Mora, Melisa Reyes-Fuentes, Cesar Queral, Edmundo Del Valle-Gallegos

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 2005-2022

Research Article / dx.doi.org/10.1080/00295450.2025.2480986

Impact of the Uncertainties Associated with Core Degradation on the State of the Corium at Vessel Rupture

Laure Carénini, Florian Fichot

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 2023-2050

Research Article / dx.doi.org/10.1080/00295450.2025.2502273

Study of the User Effect Impact in Forward Uncertainty Propagation Approaches Applied to Severe Accident

Kevin Fernández-Cosials, Cesar Queral, Miguel Sánchez-Perea, Fernando Robledo

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 2051-2066

Research Article / dx.doi.org/10.1080/00295450.2025.2508953

Investigation of the Applicability of the System Reliability Analysis Method to Identify the Cliff Edge Effect in Severe Accident Simulations

Nikolai Ryzhov, Valentina Svitelman, Kiselev Arkadi, Yudina Tatiana, Saveleva Elena

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 2067-2076

Research Article / dx.doi.org/10.1080/00295450.2025.2521588

Impact of the Uncertainties Associated with Core Degradation in H₂ Production During the In-Vessel Phase

Laure Carénini, Florian Fichot

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 2077-2100

Research Article / dx.doi.org/10.1080/00295450.2025.2525715

Application of Uncertainty and Sensitivity Analysis in Assessing the Consequences of Severe Accidents

Virginijus Vileiniškis, Tadas Kaliatka, Mindaugas Valinčius, Algirdas Kaliatka

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 2101-2132

Research Article / dx.doi.org/10.1080/00295450.2025.2526948

Evaluation of Decay Heat Calculation Uncertainties for Spent Fuel from RBMK-1500 Reactor

Andrius Slavickas, Tadas Kaliatka, Andrius Tidikas

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 2133-2146

Research Article / dx.doi.org/10.1080/00295450.2025.2528268

Iodine Source Term Uncertainty and Sensitivity Analysis with the Severe Accident Code ASTEC: Focus on Iodine Chemistry, Aerosol Behavior, and Containment Pressurization

Olivia Coindreau, Virginie Lombardi, Karine Chevalier-Jabet, Jean-Jacques Ingremeau

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 2147-2166

Research Article / dx.doi.org/10.1080/00295450.2025.2537500

Uncertainty and Sensitivity Analysis of the ASTEC Source Term Results of a MBLOCA Scenario with the Activation of Severe Accident Management Actions in a Generic Konvoi Plant

Anastasia Stakhanova, Fabrizio Gabrielli, Victor Hugo Sanchez Espinoza, Eva-Maria Pauli, Axel Hoefer

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 2167-2184

Research Article / dx.doi.org/10.1080/00295450.2025.2544372

Techniques for Sensitivity Analysis in Severe Accidents: A Comparative Study

Michela Angelucci, Luis E. Herranz, Sandro Paci

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 2185-2199

Research Article / dx.doi.org/10.1080/00295450.2025.2578869

A Summary and Future Work Plans of the Uncertainty and Sensitivity Analysis of a Severe Accident in a Generic CANDU 6 Plant in the Framework of IAEA CRP I31033

S. M. Petoukhov, A. C. Morreale, G. G. Patterson, J. H. Bae, K. I. Ahn, D. Dupleac, R-M. Nistor-Vlad

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 2200-2212

Research Article / dx.doi.org/10.1080/00295450.2025.2602406

Uncertainty Assessment of an iSMR Passive Safety System: Model Lifecycle Management Study Case

Federico Andrés Mezio, Marcelo Oscar Giménez, Pablo Gustavo Zanocco, Cristian Fabián Aramayo

Nuclear Technology / Volume 212 / Number 8 / August 2026 / Pages 2213-2222

Research Article / dx.doi.org/10.1080/00295450.2026.2639832