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Atucha II Nuclear Reactor: Design Safety and Licensing
2021-01-01 D'Auria, F.; Galassi, G. M.; Mazzantini, O.
Atucha-2 FSAR (Final Safety Analysis Report) Chapter 15, Accident Analyses
2010-01-01 D'Auria, FRANCESCO SAVERIO
BEMUSE Phase V Report Uncertainty and Sensitivity Analysis of a LBLOCA in Zion Nuclear Power Plant. OECD/NEA Report
2009-01-01 Reventós, F; BATET L., PÉREZ M; Guba, A; Toth, I; Mieusset, T; Bazin, P; DE CRECY, A; Borisov, S; Skorek, T; Glaeser, H; Joucla, J; Probst, P; Ui, A; Chung, B. D.; Oh, D. Y.; Pernica, R; Kyncl, M; Manera, A; Freixa, J; D'Auria, FRANCESCO SAVERIO; Petruzzi, A; DEL NEVO, A.
BEMUSE Programme. Phase 2 report : re-analysis of the ISP-13 exercise, post test analysis of the LOFT L2-5 test calculation
2006-01-01 D'Auria, FRANCESCO SAVERIO; Petruzzi, A; DE CRECY, A; Bazin, P; Borisov, S; Skorek, T; Glaeser, H; Benoit, J. P.; Chojnacki, E; Fujioka, K; Inoue, S; Chung, B. D.; Trosztel, I; Toth, I; Oh, D. Y.; Pernica, R; Kyncl, M; Macek, J; Macian, R; Tanker, E; Soyer, A. E.; Ozdere, O; Perez, M; Reventos, F.
Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation. IAEA Safety Report Series
2008-01-01 D'Auria, FRANCESCO SAVERIO; Glaeser, H; Lee, S; Miák, J; Modro, M; Schultz, R. R.
Boron dilution and boron transport after SBLOCA in PWR and VVER-1000 nuclear reactors, Book ‘Boron dilutation in pressurizer water reactors’
2010-01-01 Pla, P.; Parisi, C.; D'Auria, FRANCESCO SAVERIO
CERTA-TN, Consolidation of integral system experimental databases for reactor thermal-hydraulic safety analyses. European Commission Report
2003-01-01 Addabbo, C; Annunziato, A; Aksan, N; D'Auria, FRANCESCO SAVERIO; Galassi, G. M.; Dumont, D; Umminger, K; Gaul, H. P.; Nilsson, L; Hofman, D; Purhonen, H; Riikonen, V; Rigamonti, M; Steinhoff, F; Guba, A; Toth, I.
Comparison report of the OECD/CSNI International Standard Problem 21 (PIPER-ONE experiment SB-7)
1989-01-01 D'Auria, FRANCESCO SAVERIO; Mazzini, Marino; Oriolo, Francesco; Paci, Sandro
Core Exit Temperature Effectiveness in Accident Management of Nuclear Power Reactor
2010-01-01 Toth, I.; Prior, R.; Sandervag, O.; Umminger, K.; Nakamura, H.; Muellner, N.; Cherubini, Marco; Del Nevo, A.; D’Auria, F.; Dreier, J.; Alonso, J. R.; Amri, A.
Critical Flow Modelling in Nuclear Safety
1982-01-01 Brittain, I.; Karwat, H.; D'Auria, FRANCESCO SAVERIO; Vigni, P.; Hall, D. G.; Reocreux, M.
Titolo | Data di pubblicazione | Autore(i) | File |
---|---|---|---|
Atucha II Nuclear Reactor: Design Safety and Licensing | 1-gen-2021 | D'Auria, F.; Galassi, G. M.; Mazzantini, O. | |
Atucha-2 FSAR (Final Safety Analysis Report) Chapter 15, Accident Analyses | 1-gen-2010 | D'Auria, FRANCESCO SAVERIO | |
BEMUSE Phase V Report Uncertainty and Sensitivity Analysis of a LBLOCA in Zion Nuclear Power Plant. OECD/NEA Report | 1-gen-2009 | Reventós, F; BATET L., PÉREZ M; Guba, A; Toth, I; Mieusset, T; Bazin, P; DE CRECY, A; Borisov, S; Skorek, T; Glaeser, H; Joucla, J; Probst, P; Ui, A; Chung, B. D.; Oh, D. Y.; Pernica, R; Kyncl, M; Manera, A; Freixa, J; D'Auria, FRANCESCO SAVERIO; Petruzzi, A; DEL NEVO, A. | |
BEMUSE Programme. Phase 2 report : re-analysis of the ISP-13 exercise, post test analysis of the LOFT L2-5 test calculation | 1-gen-2006 | D'Auria, FRANCESCO SAVERIO; Petruzzi, A; DE CRECY, A; Bazin, P; Borisov, S; Skorek, T; Glaeser, H; Benoit, J. P.; Chojnacki, E; Fujioka, K; Inoue, S; Chung, B. D.; Trosztel, I; Toth, I; Oh, D. Y.; Pernica, R; Kyncl, M; Macek, J; Macian, R; Tanker, E; Soyer, A. E.; Ozdere, O; Perez, M; Reventos, F. | |
Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation. IAEA Safety Report Series | 1-gen-2008 | D'Auria, FRANCESCO SAVERIO; Glaeser, H; Lee, S; Miák, J; Modro, M; Schultz, R. R. | |
Boron dilution and boron transport after SBLOCA in PWR and VVER-1000 nuclear reactors, Book ‘Boron dilutation in pressurizer water reactors’ | 1-gen-2010 | Pla, P.; Parisi, C.; D'Auria, FRANCESCO SAVERIO | |
CERTA-TN, Consolidation of integral system experimental databases for reactor thermal-hydraulic safety analyses. European Commission Report | 1-gen-2003 | Addabbo, C; Annunziato, A; Aksan, N; D'Auria, FRANCESCO SAVERIO; Galassi, G. M.; Dumont, D; Umminger, K; Gaul, H. P.; Nilsson, L; Hofman, D; Purhonen, H; Riikonen, V; Rigamonti, M; Steinhoff, F; Guba, A; Toth, I. | |
Comparison report of the OECD/CSNI International Standard Problem 21 (PIPER-ONE experiment SB-7) | 1-gen-1989 | D'Auria, FRANCESCO SAVERIO; Mazzini, Marino; Oriolo, Francesco; Paci, Sandro | |
Core Exit Temperature Effectiveness in Accident Management of Nuclear Power Reactor | 1-gen-2010 | Toth, I.; Prior, R.; Sandervag, O.; Umminger, K.; Nakamura, H.; Muellner, N.; Cherubini, Marco; Del Nevo, A.; D’Auria, F.; Dreier, J.; Alonso, J. R.; Amri, A. | |
Critical Flow Modelling in Nuclear Safety | 1-gen-1982 | Brittain, I.; Karwat, H.; D'Auria, FRANCESCO SAVERIO; Vigni, P.; Hall, D. G.; Reocreux, M. |
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Opzioni
Scopri
Tipologia
- 3 Libro 88
- 3 Libro::3.1 Monografia o trattat... 88
Data di pubblicazione
- 2020 - 2021 3
- 2010 - 2019 13
- 2000 - 2009 39
- 1990 - 1999 23
- 1980 - 1989 10
Editore
- IAEA 14
- OEC D-CSNI 7
- OECD/NEA/CSNI 7
- OECD. NEA (Organisation for Econo... 5
- OECD 4
- CEC 3
- OECD/CSNI 3
- UNITED STATES NUCLEAR REGULATORY ... 3
- CEA/CENG 2
- CSNI 2
Serie
- ASME FED 1
Keyword
- FFTBM 5
- CT 3
- LOBI 3
- accuracy quantification 2
- BEMUSE 2
- code validation 2
- Large Break LOCA 2
- scaling 2
- SETF 2
- system thermal-hydraulics 2
Lingua
- eng 82
Accesso al fulltext
- no fulltext 80
- open 5
- restricted 2
- partially open 1