N. Girault
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View article: Feasibility, Effectiveness, and Cost-utility of Implementing a Reconsolidation-Based Trauma Treatment in the Aftermath of the November 13 Paris Terrorist Attacks
Feasibility, Effectiveness, and Cost-utility of Implementing a Reconsolidation-Based Trauma Treatment in the Aftermath of the November 13 Paris Terrorist Attacks Open
Background In response to the Bataclan terrorist attacks, the deadliest on French soil since World War II, the Paris Mémoire Vive (PARIS MEM) project was launched to expand the public hospital network’s capacity to treat trauma-related dis…
View article: Safety assessment for internal and external events on nuclear power plants and on mitigation strategies
Safety assessment for internal and external events on nuclear power plants and on mitigation strategies Open
This paper describes the main objectives and outcomes of two funded European projects (R2CA & BESEP), which have been recently finalized. They were dedicated to the safety analyses of design basis accidents and design extension conditions …
View article: Exploring the safety and performance of molten salt reactors for their deployment in the European Union: the MIMOSA and ENDURANCE projects
Exploring the safety and performance of molten salt reactors for their deployment in the European Union: the MIMOSA and ENDURANCE projects Open
Molten Salt Reactors (MSR) are Generation IV nuclear systems in which the fuel is dissolved in a molten salt circulating through the primary system. There is growing interest in this advanced technology in Europe, but also in the US, China…
View article: Evaluations of radionuclide activity releases into environment during loss of coolant accidents using the ASTEC code in pressurized water reactors within design basis and design extension conditions
Evaluations of radionuclide activity releases into environment during loss of coolant accidents using the ASTEC code in pressurized water reactors within design basis and design extension conditions Open
International audience
View article: Review of experimental database to support nuclear power plant safety analyses in SGTR and LOCA domains
Review of experimental database to support nuclear power plant safety analyses in SGTR and LOCA domains Open
International audience
View article: Probabilistic Safety Assessment for internal and external events on nuclear power plants and on mitigation strategies/H2020 European projects NARSIS, R2CA and BESEP
Probabilistic Safety Assessment for internal and external events on nuclear power plants and on mitigation strategies/H2020 European projects NARSIS, R2CA and BESEP Open
The NARSIS project aimed at improving assessment methodologies to be integrated into “extended Probabilistic Safety Assessment” (PSA) procedures for nuclear plants in case of single, cascade and combined external natural events. An open-ac…
View article: Evaluation of Sodium Boiling Models Using KNS-37 Loss of Flow Experiments
Evaluation of Sodium Boiling Models Using KNS-37 Loss of Flow Experiments Open
The computational codes used in the evaluation of the European sodium fast reactor—safety measures assessment and research tools(ESFR-SMART) reactor performance and specifically their sodium boiling models are assessed using two KNS-37 los…
View article: Review of Euratom projects on design, safety assessment, R&D and licensing for ESNII/Gen-IV fast neutron systems
Review of Euratom projects on design, safety assessment, R&D and licensing for ESNII/Gen-IV fast neutron systems Open
Nine Euratom projects started since late 2011 in support of the infrastructure and R&D of the seven fast reactor systems are briefly presented in the paper in terms of key objectives, results and recommendations.
View article: Paris MEM: a study protocol for an effectiveness and efficiency trial on the treatment of traumatic stress in France after the 2015–16 terrorist attacks
Paris MEM: a study protocol for an effectiveness and efficiency trial on the treatment of traumatic stress in France after the 2015–16 terrorist attacks Open
View article: System thermal-hydraulic modelling of the phénix dissymmetric test benchmark
System thermal-hydraulic modelling of the phénix dissymmetric test benchmark Open
View article: Horizon-2020 ESFR-SMART project on Sodium Fast Reactor Safety: status after 18 months
Horizon-2020 ESFR-SMART project on Sodium Fast Reactor Safety: status after 18 months Open
To improve the public acceptance of the future nuclear power in Europe we have to demonstrate that the new reactors have significantly higher safety level compared to traditional reactors. The ESFR-SMART project (European Sodium Fast React…
View article: HORIZON-2020 ESFR-SMART PROJECT ON SODIUM FAST REACTOR SAFETY: STATUS AFTER FIRST 15 MONTHS
HORIZON-2020 ESFR-SMART PROJECT ON SODIUM FAST REACTOR SAFETY: STATUS AFTER FIRST 15 MONTHS Open
Devoted to the Generation-IV European Sodium Fast Reactor safety, the Horizon-2020 ESFR-SMART project was launched in September 2017. Selected results and milestones achieved during the first fifteen months of the project are briefly revie…
View article: Horizon-2020 ESFR-SMART Project on Sodium fast reactor safety: Status after first 18 Months
Horizon-2020 ESFR-SMART Project on Sodium fast reactor safety: Status after first 18 Months Open
View article: Esfr-Smart: New Horizon-2020 Project On Sfr Safety
Esfr-Smart: New Horizon-2020 Project On Sfr Safety Open
To improve the public acceptance of the future nuclear power in Europe we have to demonstrate that the new reactors have significantly higher safety level compared to traditional reactors. The ESFR-SMART project (European Sodium Fast React…
View article: Antidepressant short-term and long-term brain effects during self-referential processing in major depression
Antidepressant short-term and long-term brain effects during self-referential processing in major depression Open
View article: ICONE23-2041 FIRST ANALYSIS OF AGS0, LT2 AND E9 CABRI TESTS WITH THE NEW SFR SAFETY CODE ASTEC-NA
ICONE23-2041 FIRST ANALYSIS OF AGS0, LT2 AND E9 CABRI TESTS WITH THE NEW SFR SAFETY CODE ASTEC-NA Open
Within the framework of the European JASMIN project, the ASTEC-Na code is being developed for safety analysis of severe accidents in SFR. In the first phase of validation of the ASTEC-Na fuel thermo-mechanical models three in-pile tests co…