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Minutes of the February 19th 2015 Steering Committee Meeting IRSN-ENEA Agreement
No full textThis document reports on achieved results and future work programs presented at the Steering Committe Meeting of the IRSN-ENEA Agreement in the field of the Nuclear Safety and Radioprotection held at the ENEA headquarters in Rome on February 19th 2015
Minutes of the September 18th 2014 Technical Meeting IRSN-ENEA Agreement
No full textThis document reports on the discussions, outcomes and actions of the Technical Meeting held at the ENEA Research Center of Bologna on September 18th for the IRSN-ENEA Agreement in the field of the Nuclear Safety and Radioprotection
Minutes of the Steering Committee IRSN-ENEA held in Rome, ENEA Headquarters, December 13th, 2018
No full textThis document reports on achieved results and future work programs presented and discussed at the Steering Committe Meeting of the IRSN-ENEA Agreement in the field of Nuclear Safety and Radioprotection held at the ENEA headquarters in Rome on December 13th 2018
HE-FUS3 benchmark results
No full textThe assessment of numerical tools for the Safety Analysis of GFR and the demonstrator ALLEGRO is the objective of the GoFastR Task 1.5.3. The available experimental data related to the HEFUS3 (ENEA Brasimone, Italy) integraI facility cooled by helium are considered with reference to the 2009 experimental campaign. Seven organizations (ENEA, PSI, AEKI/CEA, KIT, NRG, RC-Rez) are involved in the benchmark exercise with six different codes (RELAP5, TRACE, CATHARE, SIM-GFR, SPECTRA and FLUENT). The capabilities of this wide spread of transient analysis codes to describe the T/H behavior of a helium system is verified both in steady-state and transient conditions (LOFA). On the basis of a code-to-code benchmark and code-to-experiment comparison, the present document summarizes the exercise outcomes, providing the descriptions of the code models as well as the main calculation results.
Taking into account the limits of the HEFUS3 experimental data, the analysis of the results has led to a generaI positive evaluation of the codes performance, allowing to draw some recommendations on gas cooled systems modeling and the needs of future code development
LFR-120 Core neutronic verifications
No full textThis report summarizes the results of the neutronic analyses performed to verify the design of the LFR-120 core, as proposed by Hydromine Nuclear Energy S.à r.l.
Both ERANOS and MCNP have been used to investigate the specific aspects required
Risk analysis of Nuclear Power Plants against External Events
Get PDFThis report presents the activities performed in the frame of LP1, Objective B (Advanced methodologies for the evaluation of accident consequences), task B2.1 of PAR 2013, ADP ENEA-MSE. The study addresses the risk assessment of nuclear power plants due to external events, such as the earthquake and tsunami, in the light of the Fukushima accident.
As a complement to traditional deterministic analysis, safety analysis is thus implemented with probabilistic models to estimate the relative risk within a "risk-informed" framework. To this end, a few illustrative applications of the proposed methods are presented as regards, respectively, the combination of external hazards modelling and the situation of incidental Station Blackout, caused by external events
Rapporto tecnico sulle metodologie di analisi degli eventi esterni e sulla stima del rischio
Get PDFIl presente documento riporta le attività svolte nell’ambito della Linea Progettuale 1 (LP1), obiettivo B (Metodologie avanzate per la valutazione delle conseguenze incidentali), task B.2, del PAR 2012, ADP ENEA-MSE.
Lo studio presenta una metodologia del tipo “risk-informed” per la analisi di rischio di impianti nucleari a fronte di eventi esterni, così come emerge dall’incidente di Fukushima. L’approccio proposto integra gli aspetti probabilistici con quelli deterministici per perfezionare gli strumenti attualmente in uso ai fini dell’analisi di sicurezza.
Un’ applicazione pilota, in termini di definizione di sequenza dell'incidente e relativa valutazione è indicativamente proposta come significativo caso di studio. In particolare, gli incidenti di perdita di alimentazione elettrica alla centrale (o “Stazione Black-Out”) causati da eventi esterni, come tifoni e tornado, vengono analizzati sia dal punto di vista deterministico che da quello probabilistico
Post-test analysis performed by Cathare 2 v1.3u code of the Bethsy test 6.9c (OECD/CSNI ISP 38)
No full textThe document deals with the description of results obtained by the CATHARE code in the post-test simulation of the shutdown-simulation experiment performed in the Pressurized Water Reactor (PWR) experimental simulator BETHSY installed at the CEA-CENG Research Center in France. The CATHARE is the well-known computer code developed at CEA (in cooperation with EdF and Framatome) in France: the code is in use at UNIPI since more than a decade. The BETHSY is a medium-large scale Integral Test Facility (ITF) simulating with full height, full pressure, full linear power a French type PWR. The concerned test was selected as International Standard Problem 38 (ISP 38) by OECD/NEA/CSNI (Organization for Economic Cooperation and Development / Nuclear Energy Agency / Committee on the Safety of Nuclear Installations). The document describes the results of the post-test calculation submitted (by UNIPI) to CEA (French Atomic Energy Commission) after the execution of the test; however the calculation results submitted before the execution of the test are discussed. This is part of post-test analysis: the comparison of about 60 calculated time trends with measured data allows an evaluation of the capabilities of the computer code and of the code user team in predicting the scenario of an accident. This is relevant for demonstrating the capabilities in evaluating safety margins of existing NPP, with main reference to PWR accident management situation (in this case)
Going Beyond Counting First Authors in Author Co-citation Analysis
Get PDFThe present study examines one of the fundamental aspects of author co-citation analysis (ACA) - the way co-citation
counts are defined. Co-citation counting provides the data on which all subsequent statistical analyses and mappings
are based, and we compare ACA results based on two different types of co-citation counting - the traditional type that
only counts the first one among a cited work's authors on the one hand and a non-traditional type that takes into
account the first 5 authors of a cited work on the other hand. Results indicate that the picture produced through this non-traditional author co-citation counting contains more coherent author groups and is therefore considerably clearer. However, this picture represents fewer specialties in the research field being studied than that produced through the traditional first-author co-citation counting when the same number of top-ranked authors is selected and analyzed. Reasons for these effects are discussed
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