1,721,465 research outputs found
De Rosa F., "Visioni dall'impero: il cinema e la letteratura come archivio" in Le letterature africane in lingua portoghese. Temi, percorsi e prospettive
No full textBenchmarking Release, Circuit and Containment Codes against PHEBUS FP
No full textPHEBEN was a concerted action with eleven partners, benchmarking modelling codes against fission product release, circuit transport, containment aerosol physics and containment chemistry data from the in-pile experimental programme Phebus-FP. The codes gave a satisfactory overall picture of the first two tests FPT-0 and FPT-1, with generally good predictions of containment thermal hydraulics and aerosol physics. Release models performed quite well, although the predicted release of semi-volatiles was too great and the observed effect of changing fuel geometry (rod-like to melt pool) is not considered. In the circuit, codes now predict correctly that most elements are in aerosol form, but while the zone of greatest deposition is well predicted, the amount of deposition is not. Containment chemistry models for silver/iodine reactions, which can trap iodine in the sump water, so reducing its presence in the atmosphere and potentially reducing the source term, have been successfully developed and validated. Overall, the focus of severe accident research is being significantly affected by Phebus results and effort in this area is expected to continue
Nuclear Education and Training, Cause for Concern
No full textThis report is a summary of the study Nuclear Education and Training: Cause for Concern?, which was undertaken to consider the concerns raised by the OECD/NEA Member countries that nuclear education and training is decreasing, perhaps to problematic levels. Mankind now enjoys many benefits from nuclear-related technology in areas as diverse as medicine and advanced materials, as well as electricity production. Today, nuclear technology is widespread and multidisciplinary. Yet the advancement of this technology, with all its associated benefits, will be threatened, even curtailed, unless the declining number of university courses associated with it, and the declining interest among students in it, is arrested. In most countries there are now fewer comprehensive, high-quality nuclear technology programmes at universities than before. The ability of universities to attract top-quality students to those programmes, meet future staffing requirements of the nuclear industry, and conduct leading-edge research in nuclear topics is becoming seriously compromised. There currently appears to be enough trainers and quality staff in industry and at research institutes. However, the provision of suitable trainers in the near future is becoming a concern because of the university situation
Modeling of AP1000 and simulation of 10-inch cold leg small break LOCA using the CESAR thermal-hydraulic module of ASTEC
No full textThe Westinghouse AP1000 main characteristic that distinguish it with respects to the modern PWRs is the adoption of several Passive Core Cooling Systems (PCCS) to recover the normal operation or to mitigate the consequences in case of accident. In this paper, modeling and nodalisation of the Reactor Coolant System (RCS), the secondary circuit and all the PCCS for the AP1000 reactor have been studied and a 10-in. small break LOCA scenario has been analyzed using CESAR, the thermal-hydraulic module of the ASTEC V2r2 integral code. The simulation results were compared with those coming from the Westinghouse-developed NOTRUMP code used as reference, showing a reasonable agreement. In case of a 10 inches small break LOCA, the results indicate that the PCCS ensure that the fuel and cladding temperature and the other thermal-hydraulic parameters respect the safety criteria and the safety systems perform their design role during the transient, leading the plant to cold shutdown conditions. © 2015 Elsevier Ltd. All rights reserved
ASTEC AND MELCOR RESULTS COMPARED WITH AVAILABLE DATA FROM CSNI/ISP n. 46 (PHEBUS FPT1)
No full textASTEC and MELCOR are the two codes used to perform a code-to-code and a codes-to-experimental data comparison with the help of data and experimental results made available during the CSNI/ISP n. 46, related to FPT1 of the PHEBUS-FP experimental facility
Separate and Global Effects to Check the Need of Coupling between Thermal-Hydraulics and Source Term on Containment of Existing and Next LWR's
No full textHygroscopicity, A Balance of its Influence on Canpled Phenamena of Thermal Hydraulics and Source Term
No full textASTEC V1 Reactor Applications: ́Accident Sequence H2 in a French PWR 900 MWea -A MELCOR/ASTEC Comparison-
No full textDuring the first 18 months of SARNET Project, in ASTEC-RAB Working Group some calculations using the integral code ASTEC V1 have been performed focusing on the H2 severe accident sequence in a French PWR 900 MWe. In particular, ENEA compared ASTEC V1.1 results with those obtained using MELCOR 1.8.5 code. The code-to-code comparison was referred mainly to primary circuit thermal hydraulics, care degradation and containment thermal hydraulic behaviour. This part of the work was presented and discussed during the 1st ASTEC Users' Club Meeting held in Cologne in March 2005. During that meeting ENEA and other partners in the project agreed that a similar comparison should have been made also after the release of the latest versions ASTEC V1.2 and MELCOR 1.8.6. In this report are presented the main results of comparison performed using new code versions
Gruppo di Lavoro MILLE600: Repertorio dati per un reattore PWR come caso di esercizio per codici di analisi di sicurezza e di PSA
Full text linkNell'ambito dell'Accordo di Programma ENEA - Ministero dello Sviluppo Economico e dell'Accordo di Programma ERSE (ENEA - Ricerca sul Sistema Elettrico) - Ministero dello Sviluppo Economico, è stato creato un gruppo di lavoro specialistico finalizzato alla rivitalizzazione in Italia delle competenze in materia nucleare, con particolare attenzione agli aspetti di sicurezza. Questo gruppo, che ha assunto la denominazione di 'Gruppo di Lavoro MILLE600', è coordinato da ENEA UTFISSM con ERSE che funge da Segretario Scientifico. In questo documento sono descritte le principali caratteristiche di una generica centrale elettronucleare di potenza, basata su un reattore PWR da 1600 MWe di ultima generazione. In particolare, il documento contiene dati utili alla realizzazione e al collaudo di modelli di calcolo e simulazione, nonché all'allestimento di studi teorici e sperimentali, autoconsistenti e confrontabili, da parte di università ed istituzioni di ricerca
H2 SEQUENCE IN A FRENCH PWR 900 MWe: COMPARISON BETWEEN MELCOR AND ASTEC CODES
No full textIn order to evaluate the reliability, stability and robustness of the V1.1 version of ASTEC code, a comparison with MELCOR code, referring to the H2 sequence in a French PWR 900 MWe, has been performed by ENEA FIS/NUC in the ambit of the RAB (Reactor Application and Benchmarking) work package of SARNET-ASTEC. This is the first time that a French REP900 is modelled using MELCOR. In this report only the first part of the whole planned work is reported. The remaining work, consisting of additional and more detailed code-to-code comparisons, will be performed after the release of new code versions, both for ASTEC (by July 2005) and MELCOR (by September/October 2005)
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