Research graph
References from A PSA-informed methodology for alternative source term evaluation in HPR1000. Local targets link to admitted publications; unresolved targets remain external evidence.
Advanced and small modular reactors' supply chain: current status and potential for global cooperation
10.1016/j.pnucene.2025.105661 · 2025 · External reference
The APR1400 SOARCA study: insights into the evolution of severe accidents and fission product source term analysis results
10.1016/j.pnucene.2023.104628 · 2023 · External reference
Uncertainty quantification for severe-accident reactor modelling: set-Up and first results of the Horizon-2020 project MUSA
10.1016/j.anucene.2023.109919 · 2023 · External reference
Uncertainty quantification for severe-accident reactor modelling: results and conclusions of the MUSA reactor applications work package
10.1016/j.anucene.2024.110962 · 2025 · External reference
A comparison of existing bootstrap algorithms for multi-stage sampling designs
10.3390/stats5020031 · 2022 · External reference
Bootstrap methods: another look at the jackknife
1992 · External reference
Unresolved reference
1993 · External reference
Post-operation radiological source term and dose rate estimates for the scalable liquid Metal-cooled small Modular Reactor
10.1016/j.anucene.2018.02.001 · 2018 · External reference
Inventory and solubility of fission products in molten lead to quantify source term in lead-cooled fast reactors
10.1016/j.anucene.2024.110357 · 2024 · External reference
Unresolved reference
2010 · External reference
Best-estimate severe accident and source term analysis for an ISLOCA scenario of a CANDU-6 plant using the MAAP-ISAAC code
10.1016/j.nucengdes.2019.110443 · 2020 · External reference
Unresolved reference
1986 · External reference
Sensitivity analysis ON key parameters OF severe accident source term of PWR
2022 · External reference
Simulation research on real-time offsite dose radiation of nuclear power plant
2022 · External reference
Aerosol behavior model development and validation of SPRUCE code source term module
2026 · External reference
Simulation of passive containment cooling System in severe accident via ASTEC
2026 · External reference
Research of aerosol removal by passive containment cooling system
10.1016/j.jandt.2024.05.004 · 2023 · External reference
Uncertainty and sensitivity analysis of containment aerosol removal under severe accident
10.1016/j.pnucene.2025.106004 · 2026 · External reference
Simulation of thermohydraulics and aerosol behavior in LACE LA4 via SPRUCE
2026 · External reference
Uncertainty analysis of radionuclide release into containment during severe accidents: application of MELCOR 2.2 to the PHEBUS FPT-1 test
2026 · External reference
Radiological consequence assessments using time-varying source terms in ONERS- decision support system for nuclear emergency response
10.1016/j.pnucene.2020.103436 · 2020 · External reference
Design and performance analysis of high-power lead-bismuth cooled micro reactor
10.1016/j.anucene.2026.112115 · 2026 · External reference
Simulation of fission product release in PHEBUS FPT1 via SPRUCE
2026 · External reference
Development of a source-term migration model for a large bubble formed in a core disruptive accident
10.1016/j.jaerosci.2024.106482 · 2025 · External reference
Post-operation radiological source term and dose rate estimates for the scalable liquid Metal-cooled small Modular Reactor
10.1016/j.anucene.2018.02.001 · ExternalCitation · doi-reference
Uncertainty quantification for severe-accident reactor modelling: set-Up and first results of the Horizon-2020 project MUSA
10.1016/j.anucene.2023.109919 · ExternalCitation · doi-reference
Inventory and solubility of fission products in molten lead to quantify source term in lead-cooled fast reactors
10.1016/j.anucene.2024.110357 · ExternalCitation · doi-reference
Uncertainty quantification for severe-accident reactor modelling: results and conclusions of the MUSA reactor applications work package
10.1016/j.anucene.2024.110962 · ExternalCitation · doi-reference
Design and performance analysis of high-power lead-bismuth cooled micro reactor
10.1016/j.anucene.2026.112115 · ExternalCitation · doi-reference
Development of a source-term migration model for a large bubble formed in a core disruptive accident
10.1016/j.jaerosci.2024.106482 · ExternalCitation · doi-reference
Research of aerosol removal by passive containment cooling system
10.1016/j.jandt.2024.05.004 · ExternalCitation · doi-reference
Best-estimate severe accident and source term analysis for an ISLOCA scenario of a CANDU-6 plant using the MAAP-ISAAC code
10.1016/j.nucengdes.2019.110443 · ExternalCitation · doi-reference
Radiological consequence assessments using time-varying source terms in ONERS- decision support system for nuclear emergency response
10.1016/j.pnucene.2020.103436 · ExternalCitation · doi-reference
The APR1400 SOARCA study: insights into the evolution of severe accidents and fission product source term analysis results
10.1016/j.pnucene.2023.104628 · ExternalCitation · doi-reference
Advanced and small modular reactors' supply chain: current status and potential for global cooperation
10.1016/j.pnucene.2025.105661 · ExternalCitation · doi-reference
Uncertainty and sensitivity analysis of containment aerosol removal under severe accident
10.1016/j.pnucene.2025.106004 · ExternalCitation · doi-reference
A comparison of existing bootstrap algorithms for multi-stage sampling designs
10.3390/stats5020031 · ExternalCitation · doi-reference
