Sfoglia
Prodotti della tipologia (ordinati per Data di deposito in Decrescente ordine): 1.361 a 1.380 di 1.701
HE-FUS3 Loop: Data Sheets for Code Modelling and Experimental Data for Code Assessment
2008-05-15 Polidori, M.
ELSY Neutronic Analysis: Status of the Open Square Design
2008-12-01 Artioli, C.; Sarotto, M.
ELSY core design static, dynamic and safety parameters with the open square FA
2009-11-26 Sarotto, M.
ELSY PROJECT: SPECIFICATION OF THE CONTAINMENT SYSTEM
2009-05-20 De Rosa, F.
Comparative Assessment of Empirical Correlations for Single-Phase Heat Transfer in Rod Bundles of HLM Cooled Reactors
2007-04-27 Antonucci, C.
ELSY Open Square Fuel Assembly Design and Drawings
2008-11-04 Grasso, G.; Artioli, C.; Sarotto, M.
EFIT/ELSY - Pressure Drop Performance of the Rod Bundle
2007-11-21 Antonucci, C.
Analisi CFD del Comportamento Termoidraulico del Nocciolo per il Reattore Raffreddato a Piombo ELSY
2007-11-21 Marchetti, M.
Activity Report of the ENEA Nuclear Data Project in 2008
2009-03-17 Ventura, A.
Dosimetry Cross Section Processing from IRDF-2002 in the BUGLE-96 (47 n) Neutron Group Structure
2009-09-22 Orsi, R.
MATJEFF31.BOLIB - A JEFF-3.1 Multi-Group Coupled (199 n + 42gamma) Cross Section Library in MATXS Format for Nuclear Fission Applications
2009-05-05 Pescarini, M.
Generation and Preliminary Testing of ENEA-Bologna BUGLE-Type Group Libraries Based on JEFF-3.1 and ENDF/B-VII.0 Nuclear Data for LWR Shielding and Pressure Vessel Dosimetry
2008-10-03 Pescarini, M.; Orsi, R.
ADEFTA Version 4.1: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis
2008-05-20 Orsi, R.
B0T3P Version 5.3: A Pre/Post-Processor System for Transport Analysis
2008-10-22 Orsi, R.
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P
2007-08-10 Orsi, R.
Activity Report of the ENEA Nuclear Data Project in 2007
2008-03-18 Ventura, A.
ENEA-Bologna Production and Testing or JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications
2007-06-07 Orsi, R.; Pescarini, M.
ADEFTA Version 4.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis
2007-04-17 Orsi, R.
VITJEFF31.BOLIB - A JEFF-3.1 Multi-Group Coupled (199 n + 42γ) Cross Section Library in AMPX Format for Nuclear Fission Applications
2008-02-18 Pescarini, M.
ENEA-Bologna 2007 Revision of the SCAMPI (ORNL) Nuclear Data Processing System
2007-09-13 Pescarini, M.
Prodotti della tipologia (ordinati per Data di deposito in Decrescente ordine): 1.361 a 1.380 di 1.701
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Scopri
Tipologia
- 5 Documenti e prodotti tecnici1701
Data di pubblicazione
- 2020 - 202576
- 2010 - 20191093
- 2000 - 2009531
- 1999 - 19991
Editore
- ENEA737
- ENEA - UTS Tecnologie fisiche ava...150
- ENEA - UTS Protezione e sviluppo ...89
- ENEA - Unità di Agenzia per lo sv...3
- ENEA - Centro di Bologna1
- ENEA - Senior Board1
Keyword
- Rapporto tecnico1200
- Generation IV reactors246
- Sicurezza nucleare217
- Reattori nucleari ad acqua144
- Valutazione del ciclo di vita142
- Neutronica135
- Tecnologia dei metalli liquidi103
- Reattori sottocritici/ADS95
- Reattori nucleari veloci92
- Disattivazione impianti nucleari84
Lingua
- it499
- en236
- ita59
- eng22
Accesso al fulltext
- no fulltext993
- open708