Francesco Saverio D'Auria
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View article: Nuclear power technology: an analysis and informed opinions
Nuclear power technology: an analysis and informed opinions Open
“We have opinions, we make observations, we change our opinions.” Stephen Senn, Dicing with Death , 2003. The purpose of this review paper is to inform debate and provide snapshot opinions about challenges and solutions for the development…
View article: OECD/NEA/CSNI state-of-the-art report on scaling in system thermal-hydraulics applications to nuclear reactor safety and design (The S-SOAR)
OECD/NEA/CSNI state-of-the-art report on scaling in system thermal-hydraulics applications to nuclear reactor safety and design (The S-SOAR) Open
The present paper deals with scaling in nuclear-system thermal-hydraulics (SYS TH), including the connection with Nuclear Reactor Safety Technology (NST). The paper is entirely derived from the S-SOAR document issued by CSNI of NEA, NEA/CS…
View article: Summary from “Aix-en-Provence 1992” and “Annapolis 1996” OECD/NEA/CSNI Specialists Meetings in Nuclear Thermal Hydraulics
Summary from “Aix-en-Provence 1992” and “Annapolis 1996” OECD/NEA/CSNI Specialists Meetings in Nuclear Thermal Hydraulics Open
The Committee on the Safety of Nuclear Installations of Nuclear Energy Agency part of the Organization for
\nEconomic Cooperation and Development (shortly, OECD/NEA/CSNI) has an internationally recognized role in
\nthe development and impr…
View article: Small Modular Reactors Licensing Process Based on BEPU Approach: Status and Perspective
Small Modular Reactors Licensing Process Based on BEPU Approach: Status and Perspective Open
The competitiveness of small modular reactors (SMRs) has been planned based on design simplification, short construction time, passive safety systems, and enabling self-financing by ramp-up construction. Due to the global energy challenges…
View article: Analysis of loss of cooling accident in VVER-1000/V446 spent fuel pool using RELAP5 and MELCOR codes
Analysis of loss of cooling accident in VVER-1000/V446 spent fuel pool using RELAP5 and MELCOR codes Open
Following the Fukushima nuclear disaster, the simulation of accidents in the spent fuel pool has become more noticeable. Despite the low amount of decay heat power, the consequences of the accidents in a spent fuel pool (SFP) can be severe…
View article: Nuclear Fuel Modelling During Power Ramp
Nuclear Fuel Modelling During Power Ramp Open
Fuel rods operating for several years in a LWR can experience fuel-cladding gap closure as a result of the phenomena due to temperature and irradiation. Local power increase induces circumferential stresses in the cladding as a result of t…
View article: Innovation needs in nuclear reactor safety and risk
Innovation needs in nuclear reactor safety and risk Open
After three quarters of a century using nuclear fission to produce energy, Nuclear Reactor Safety and Risk constitutes an established technological sector. A key feature is continuous updating following new discoveries and progress in know…
View article: Application of Best Estimate Plus Uncertainty (BEPU) Methodology in a Final Safety Analysis Report (FSAR) of a Generic Plant
Application of Best Estimate Plus Uncertainty (BEPU) Methodology in a Final Safety Analysis Report (FSAR) of a Generic Plant Open
The licensing process of a nuclear power plant is motivated by the need to protect humans and the environment from ionizing radiation and, at the same time, sets out the basis for the design and determining the acceptability of the plant. …
View article: Prioritizing Pressure Drop Research in Nuclear Thermal Hydraulics
Prioritizing Pressure Drop Research in Nuclear Thermal Hydraulics Open
View article: Identification of Thermalhydraulic Phenomena for Pwr Transient Analysis and Simulation
Identification of Thermalhydraulic Phenomena for Pwr Transient Analysis and Simulation Open
View article: Physical Phenomena in Nuclear Thermal Hydraulics and Current Status
Physical Phenomena in Nuclear Thermal Hydraulics and Current Status Open
116 nuclear Thermal-Hydraulic Phenomena T-HP are identified in the present paper, following documents issued during the last three decades by the Committee on the Safety of Nuclear Installations of Nuclear Energy Agency of the Organization…
View article: Challenges and concerns for development of nuclear thermal-hydraulics
Challenges and concerns for development of nuclear thermal-hydraulics Open
View article: Critical flow prediction by system codes – Recent analyses made within the FONESYS network
Critical flow prediction by system codes – Recent analyses made within the FONESYS network Open
View article: Nuclear Energy and Its History: Past Consequences, Present Inadequacies and a Perspective for Success
Nuclear Energy and Its History: Past Consequences, Present Inadequacies and a Perspective for Success Open
An attempt is made to locate nuclear technology within a logical context considering history, risks, societal catastrophes and perspectives: the need is identified for a new direction in the exploitation in order to restore the role in ene…
View article: Meet Our Regional Editor
Meet Our Regional Editor Open
View article: The technological challenge for current generation nuclear reactors
The technological challenge for current generation nuclear reactors Open
The present paper deals with the proposal of an additional safety barrier for the class of large (1000 MWe or more) Light Water Reactors (LWR) now in operation, in construction, or under design. Emphasis is given to the motivations or the …
View article: Reprint of “The role of nuclear thermal-hydraulics in the licensing of Atucha-II: The LBLOCA”
Reprint of “The role of nuclear thermal-hydraulics in the licensing of Atucha-II: The LBLOCA” Open
The paper deals with the safety evaluation and the embedded licensing process of the Atucha-II 800 Mwe Pressurized Heavy Water Reactor (PHWR) in Argentina. Atucha-II was designed by Kraftwerk Union (KWU) during the 60’s, the related constr…
View article: Nuclear thermal-hydraulics: What is it?
Nuclear thermal-hydraulics: What is it? Open
View article: V&V&C in nuclear reactor thermal-hydraulics
V&V&C in nuclear reactor thermal-hydraulics Open
View article: Prioritization of nuclear thermal-hydraulics researches
Prioritization of nuclear thermal-hydraulics researches Open
View article: Introduction of an Additional Safety Barrier for Nuclear Power Reactors
Introduction of an Additional Safety Barrier for Nuclear Power Reactors Open
In the present paper a proposal is formulated to improve the safety of existing and future nuclear reactors. The idea is based upon the introduction of a new safety barrier against the release of radioactivity generated by the fission chai…
View article: New turbulence modeling for simulation of Direct Contact Condensation in two-phase pressurized thermal shock
New turbulence modeling for simulation of Direct Contact Condensation in two-phase pressurized thermal shock Open
View article: Introducing V&V&C in Nuclear Thermal-Hydraulics
Introducing V&V&C in Nuclear Thermal-Hydraulics Open
V&V constitutes a powerful framework to demonstrate the capability of computational tools in several technological areas. Passing V&V requirements is a needed step before applications. Let’s focus hereafter to the area of (transient) Nucle…
View article: This special issue of Nuclear Engineering and Design collects selected papers from the “specialists workshop on advanced instrumentation and measurement techniques for nuclear reactor thermal-hydraulics” (SWINTH), held in Livorno, Italy, on June 2016
This special issue of Nuclear Engineering and Design collects selected papers from the “specialists workshop on advanced instrumentation and measurement techniques for nuclear reactor thermal-hydraulics” (SWINTH), held in Livorno, Italy, on June 2016 Open
View article: Panel Session: Reliability of Passive Systems
Panel Session: Reliability of Passive Systems Open
Passive systems are embedded into the nuclear technology
\nsafety and design. In relation to safety, accumulators are one example
\nof vital passive systems strictly needed to mitigate consequences of
\nLarge Break LOCA. In relation to des…
View article: Instrumenting full-scale Boron Injection Test Facility to support Atucha-2 NPP licensing
Instrumenting full-scale Boron Injection Test Facility to support Atucha-2 NPP licensing Open
View article: An overview of Thorium Utilization in Nuclear Reactors and Fuel Cycle
An overview of Thorium Utilization in Nuclear Reactors and Fuel Cycle Open
The Nuclear Power Plants (NPP) constructed in the XX century, also called generation II
\nreactors, are still in operation, most of them Light Water Reactors, but are being decommissioned.
\nThese reactors have a low burn up (~30 MWD/kg U)…
View article: Hyperbolicity and numerics in SYS-TH codes: The FONESYS point of view
Hyperbolicity and numerics in SYS-TH codes: The FONESYS point of view Open
View article: Validation of NEPTUNE CFD two-phase flow models against OECD/NRC PSBT subchannel experiments
Validation of NEPTUNE CFD two-phase flow models against OECD/NRC PSBT subchannel experiments Open
View article: BEPU-FSAR: A new paradigm in Nuclear Reactor Safety
BEPU-FSAR: A new paradigm in Nuclear Reactor Safety Open
Nuclear safety has become a technology following extraordinary industrial investments since the 50’s. Events in the last decades occurring in the Three Mile Island Unit-2, Chernobyl Unit-4 and Fukushima Units 1-3 have challenged the sustai…