-
1
-
-
77957715510
-
CSNI code validation matrix of thermo-hydraulic codes for LWR LOCA and transients
-
Paris (F), March
-
Aksan S.R., Bessette D., Brittain I., D'Auria F., Gruber P., Holmstrom H.L.O., Landry R., Naff S., Pochard R., Preusche G., Reocreux M., Sandervag O., Stadtke H., Wolfert K., Zuber No. (1987) CSNI Code Validation Matrix of Thermo-Hydraulic Codes for LWR LOCA and Transients. CSNI Report No. 132, Paris (F), March.
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CSNI Report No. 132
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Aksan, S.R.1
Bessette, D.2
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D'Auria, F.4
Gruber, P.5
Holmstrom, H.L.O.6
Landry, R.7
Naff, S.8
Pochard, R.9
Preusche, G.10
Reocreux, M.11
Sandervag, O.12
Stadtke, H.13
Wolfert, K.14
Zuber, N.15
-
3
-
-
0042963684
-
-
OECD-CSNI Report OCDE/GD(94)82, Paris (F), September
-
Aksan S.N., D'Auria, F., Glaeser H., Pochard R., Richards C., Sjoberg A. (1993) Separate Effects Test Matrix for Thermalhydraulic Code Validation: Phenomena Characterisation and Selection of Facilities and Tests - Vol. I". OECD-CSNI Report OCDE/GD(94)82, Paris (F), September.
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Separate Effects Test Matrix for Thermalhydraulic Code Validation: Phenomena Characterisation and Selection of Facilities and Tests
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Aksan, S.N.1
D'Auria, F.2
Glaeser, H.3
Pochard, R.4
Richards, C.5
Sjoberg, A.6
-
4
-
-
0041460757
-
The Italian experience on T/H best estimate codes: Achievement and perspectives
-
November 1996
-
Alemberti A., D'Auria F., Fiorino E., Galassi G.M., Marella G., Marsili P., Meloni P., Naviglio A. (1996) The Italian experience on T/H best estimate codes: achievement and perspectives (to be issued), CSNI Specialist Meeting Annapolis, November 1996
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(1996)
CSNI Specialist Meeting Annapolis
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-
Alemberti, A.1
D'Auria, F.2
Fiorino, E.3
Galassi, G.M.4
Marella, G.5
Marsili, P.6
Meloni, P.7
Naviglio, A.8
-
5
-
-
0041460752
-
Blowdown phenomenon: Critical analysis of some calculation models for the safety analysis of nuclear power plants
-
Torino (I), 25-27 June
-
Ambrosini W., D'Auria F., Vigni P. (1987) Blowdown Phenomenon: Critical Analysis of some Calculation Models for the Safety Analysis of Nuclear Power Plants. 5th Conf. of Italian Society of Heat Transport. Torino (I), 25-27 June.
-
(1987)
5th Conf. of Italian Society of Heat Transport
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-
Ambrosini, W.1
D'Auria, F.2
Vigni, P.3
-
7
-
-
0041460755
-
Application of the CATHARE advanced code to numerical benchnark exercises
-
Rome (I), 23-24 March
-
Ambrosini W., Bestion D., D'Auria F., De Pasquale F., Micaelli J.C., Tempini M. (1989) Application of the CATHARE Advanced Code to Numerical Benchnark Exercises. EUROTHERM Seminar N. 7: Thermal Non-Equilibrium in Two-Phase Flow, Rome (I), 23-24 March.
-
(1989)
EUROTHERM Seminar N. 7: Thermal Non-equilibrium in Two-phase Flow
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-
Ambrosini, W.1
Bestion, D.2
D'Auria, F.3
De Pasquale, F.4
Micaelli, J.C.5
Tempini, M.6
-
8
-
-
0002444379
-
Evaluation of accuracy of thermalhydraulic codes calculations
-
May
-
Ambrosini W., Bovalini R., D'Auria F. (1990) Evaluation of Accuracy of Thermalhydraulic Codes Calculations, J. Energia Nucleare, Vol. 7 N. 2, May.
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(1990)
J. Energia Nucleare
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, Issue.2
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Ambrosini, W.1
Bovalini, R.2
D'Auria, F.3
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11
-
-
0041961920
-
The multidimensional module of cathare 2
-
Saratoga Springs, September
-
Barre F., Dor I., Sun C. (1995) The multidimensional module of Cathare 2. NURETH 7 Conference., Saratoga Springs, September.
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(1995)
NURETH 7 Conference
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-
Barre, F.1
Dor, I.2
Sun, C.3
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13
-
-
0042963680
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Application of a statistical model to the evaluation of counterpart test data base
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Belsito S., D'Auria F., Galassi G. M. (1994a) Application of a Statistical model to the evaluation of Counterpart Test data base, J. Kerntechnik, Vol 59 Nr 3.
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(1994)
J. Kerntechnik
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, Issue.3
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14
-
-
0041460741
-
-
University of Pisa Report, DCMN - NT 282(96), Pisa (I), May
-
Belsito S., D'Auria F. (1996) Advancements in the application of UMAE to the OECD/CSNI uncertainty method study, University of Pisa Report, DCMN - NT 282(96), Pisa (I), May.
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Advancements in the Application of UMAE to the OECD/CSNI Uncertainty Method Study
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-
Belsito, S.1
D'Auria, F.2
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15
-
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0042462520
-
Application of Relap5/Mod2 to PWR international standard problems
-
San Francisco (Ca), 10-15 November
-
Billa C., D'Auria F., Debrecin N., Galassi G.M. (1991) Application of Relap5/Mod2 to PWR International Standard Problems, ANS Winter Meeting, San Francisco (Ca), 10-15 November.
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(1991)
ANS Winter Meeting
-
-
Billa, C.1
D'Auria, F.2
Debrecin, N.3
Galassi, G.M.4
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16
-
-
0042963685
-
OECD NEA sample problem analysis with RELAP5/MOD1-019 computer code
-
Paris (F), 28-29 November
-
Boccaccini L., D'Auria F., Galassi G.M., Oriolo F., Paci S. (1983) OECD NEA Sample Problem Analysis with RELAP5/MOD1-019 Computer Code, Workshop on Computer Aspects of the RELAPS Program, Paris (F), 28-29 November.
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(1983)
Workshop on Computer Aspects of the RELAPS Program
-
-
Boccaccini, L.1
D'Auria, F.2
Galassi, G.M.3
Oriolo, F.4
Paci, S.5
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17
-
-
77957715272
-
A methodology for the qualification of thermalhydraulic codes nodalizations
-
Grenoble (F), 5-8 October
-
Bonuccelli M., D'Auria F., Debrecin N., Galassi G.M. (1993) A methodology for the qualification of thermalhydraulic codes Nodalizations, 6th International Top. Meet. on Nuclear Reactor Thermalhydraulics, Grenoble (F), 5-8 October.
-
(1993)
6th International Top. Meet. on Nuclear Reactor Thermalhydraulics
-
-
Bonuccelli, M.1
D'Auria, F.2
Debrecin, N.3
Galassi, G.M.4
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18
-
-
0026746907
-
Analysis of counterpart tests performed in BWR experimental simulators
-
Bovalini R., D'Auria F., De Varti A., Maugeri P., Mazzini M. (1992) Analysis of Counterpart Tests performed in BWR Experimental Simulators. J. Nuclear Technology, vol 97 Nr. 1.
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(1992)
J. Nuclear Technology
, vol.97
, Issue.1
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-
Bovalini, R.1
D'Auria, F.2
De Varti, A.3
Maugeri, P.4
Mazzini, M.5
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19
-
-
0041961918
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Experimental analysis of density waves instability in PIPER-ONE apparatus
-
Milan (I), 24-26 June
-
Bovalini R., D'Auria F., Mazzini M., Virdis M. (1993) Experimental Analysis of density waves instability in PIPER-ONE apparatus. 11th Conference of Italian Society of Heat Transport, Milan (I), 24-26 June.
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(1993)
11th Conference of Italian Society of Heat Transport
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-
Bovalini, R.1
D'Auria, F.2
Mazzini, M.3
Virdis, M.4
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21
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0041460754
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PIPER-ONE research: Experimental study of gas injection on isolation condenser performance
-
Rome, June
-
Bovalini R., D'Auria F., Guerrini B., Mazzini M. (1996) PIPER-ONE research: experimental study of gas injection on isolation condenser performance. 2nd European Thermal Science and 14th UIT National Heat Transfer Conference, Rome, June.
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(1996)
2nd European Thermal Science and 14th Uit National Heat Transfer Conference
-
-
Bovalini, R.1
D'Auria, F.2
Guerrini, B.3
Mazzini, M.4
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22
-
-
0038440737
-
The thermalhydraulic code ATHLET for analysis of PWR and BWR systems
-
Karslruhe - Germany, October
-
Burnell M.J., Lerchl G., Miro J., Teschendorff V., Wolfert K. (1989) The thermalhydraulic code ATHLET for analysis of PWR and BWR systems. NURETH-4 Conference., Karslruhe - Germany, October.
-
(1989)
NURETH-4 Conference
-
-
Burnell, M.J.1
Lerchl, G.2
Miro, J.3
Teschendorff, V.4
Wolfert, K.5
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23
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0041961916
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-
University of Pisa Report, DCMN - RL 290(87), Pisa (I), December
-
Camiciola P., D'Auria F., Marsili P., Petrini P. (1987) OECD/CSNI ISP 20: post-test calculations and sensitivity analyses by RELAP5/MOD2 performed with reference to the SGTR accident occurred at DOEL-2 NPP. University of Pisa Report, DCMN - RL 290(87), Pisa (I), December.
-
(1987)
OECD/CSNI ISP 20: Post-test Calculations and Sensitivity Analyses by RELAP5/MOD2 Performed with Reference to the SGTR Accident Occurred at DOEL-2 NPP
-
-
Camiciola, P.1
D'Auria, F.2
Marsili, P.3
Petrini, P.4
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24
-
-
0020603201
-
BLOWAES: A method to evaluate blowdown two-phase flowrate from pressure and thrust measurements
-
Santa Barbara (CA), 11-14 January
-
D'Auria F., Vigni P. (1983) BLOWAES: a Method to Evaluate Blowdown Two-Phase Flowrate from Pressure and Thrust Measurements. 2nd International Top. Meeting on Nuclear Reactor Thermalhydraulics, Santa Barbara (CA), 11-14 January.
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(1983)
2nd International Top. Meeting on Nuclear Reactor Thermalhydraulics
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-
D'Auria, F.1
Vigni, P.2
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27
-
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0022078734
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Assessment of scaling principles for the simulation of small break LOCA experiments in PWRs
-
D'Auria F., Galassi G.M., Oriolo F., Vigni P. (1987) Assessment of Scaling Principles for the Simulation of Small Break LOCA Experiments in PWRs. J. Nuclear Engineering & Design, Vol 102.
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(1987)
J. Nuclear Engineering & Design
, vol.102
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-
D'Auria, F.1
Galassi, G.M.2
Oriolo, F.3
Vigni, P.4
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29
-
-
0041460749
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Analysis by RELAP5/MOD2 of a loss of feedwater transient in the Leibstadt BWR-6 plant
-
Avignon (F), 3-7 October
-
D'Auria F., Maugeri P. (1988) Analysis by RELAP5/MOD2 of a Loss of Feedwater Transient in the Leibstadt BWR-6 Plant. International Conference on Thermal Reactor Safety, Avignon (F), 3-7 October.
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(1988)
International Conference on Thermal Reactor Safety
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-
D'Auria, F.1
Maugeri, P.2
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30
-
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0042462519
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Assessment of RELAP5/mod2 and RELAP5/MOD1-EUR codes on the basis of LOBI-MOD2 test results - Final report
-
Luxembourg (L)
-
D'Auria F., Mazzini M., Oriolo F., Galassi G.M. (1989) Assessment of RELAP5/MOD2 and RELAP5/MOD1-EUR Codes on the Basis of LOBI-MOD2 Test Results - Final Report. CEC Report EUR 12403 EN, Luxembourg (L).
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(1989)
CEC Report EUR 12403 EN
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-
D'Auria, F.1
Mazzini, M.2
Oriolo, F.3
Galassi, G.M.4
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31
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0041460747
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The application of CATHARE 1 v1.3 to LOBI small break LOCA experiments and a comparison with RELAP5/mod2 - Final report
-
Luxembourg (L)
-
D'Auria F., Galassi G.M. (1989) The Application of CATHARE 1 v1.3 to LOBI Small Break LOCA Experiments and a Comparison with RELAP5/MOD2 - Final Report. CEC Report EUR 12404 EN, Luxembourg (L).
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(1989)
CEC Report EUR 12404 EN
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D'Auria, F.1
Galassi, G.M.2
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32
-
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0042462517
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performed by RELAP5/MOD2 code in the frame of a cooperation with University of Zagreb and ENEA, OECD CSNI Workshop on ISP 26, Grenoble (F), 6-8 June
-
D'Auria F., Galassi G.M., Billa C., Debrecin N. (1990) OECD CSNIISP 26: post-test analysis of a Small Break LOCA in the LSTF Facility performed by RELAP5/MOD2 code in the frame of a cooperation with University of Zagreb and ENEA, OECD CSNI Workshop on ISP 26, Grenoble (F), 6-8 June.
-
(1990)
OECD CSNIISP 26: Post-test Analysis of a Small Break LOCA in the LSTF Facility
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D'Auria, F.1
Galassi, G.M.2
Billa, C.3
Debrecin, N.4
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33
-
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85045808019
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Assessment of RELAP5/MOD2 code on the basis of experiments performed in LOBI facility
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D'Auria F., Galassi G. M. (1990) Assessment of RELAP5/MOD2 Code on the Basis of Experiments Performed in LOBI Facility. J. Nuclear Technology, Vol 90, Nr. 3.
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(1990)
J. Nuclear Technology
, vol.90
, Issue.3
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D'Auria, F.1
Galassi, G.M.2
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34
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0025519372
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Characterization of instabilities during two-phase natural circulation in PWR typical conditions
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D'Auria F., Galassi G.M. (1990a) Characterization of Instabilities during Two-Phase Natural Circulation in PWR Typical Conditions. J. Experimental Thermal and Fluid Science, Vol 3, Nr 90.
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(1990)
J. Experimental Thermal and Fluid Science
, vol.3
, Issue.90
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D'Auria, F.1
Galassi, G.M.2
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35
-
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0006030629
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Flowrate and density oscillations during two-phase natural circulation in PWR typical conditions
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D'Auria F., Galassi G.M. (1990b) "Flowrate and Density Oscillations During Two-Phase Natural Circulation in PWR Typical Conditions. J. Nuclear Engineering & Design, Vol. 122.
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(1990)
J. Nuclear Engineering & Design
, vol.122
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D'Auria, F.1
Galassi, G.M.2
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37
-
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0000169692
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Scaling of natural circulation in PWR systems
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D'Auria F., Galassi G.M., Vigni P., Calastri A. (1992) Scaling of Natural Circulation in PWR Systems. J. Nuclear Engineering & Design, vol 132 Nr. 2.
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(1992)
J. Nuclear Engineering & Design
, vol.132
, Issue.2
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D'Auria, F.1
Galassi, G.M.2
Vigni, P.3
Calastri, A.4
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38
-
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0041460745
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Application of RELAP5/MOD2 system code to small break LOCA counterpart experiments in PWR simulators
-
Caxambu, Minas Gerais (BRA), 25-29 October
-
D'Auria F., Debrecin N., Galassi G.M. (1993) Application of RELAP5/MOD2 system code to small break LOCA counterpart experiments in PWR simulators. IX Brazilian Meeting on Reactor Physics and Thermalhydraulics, Caxambu, Minas Gerais (BRA), 25-29 October.
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(1993)
IX Brazilian Meeting on Reactor Physics and Thermalhydraulics
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D'Auria, F.1
Debrecin, N.2
Galassi, G.M.3
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39
-
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0041460744
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Relevant thermalhydraulic aspects of new generation LWR's
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D'Auria F., Modro M., Oriolo F., Tasaka K. (1993a) Relevant Thermalhydraulic Aspects of New Generation LWR's. J. Nuclear Engineering & Design, Vol 145, Nrs. 1&2.
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(1993)
J. Nuclear Engineering & Design
, vol.145
, Issue.1-2
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D'Auria, F.1
Modro, M.2
Oriolo, F.3
Tasaka, K.4
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40
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0343345560
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Application of RELAP5/MOD3 to the evaluation of loss of feedwater in test facilities and in nuclear plants
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D'Auria F., Debrecin N., Galassi G.M., Galeazzi S. (1993b) Application of RELAP5/MOD3 to the Evaluation of Loss of Feedwater in test Facilities and in Nuclear Plants. J. Nuclear Engineering & Design, Vol 141, Nr 3.
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(1993)
J. Nuclear Engineering & Design
, vol.141
, Issue.3
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D'Auria, F.1
Debrecin, N.2
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Galeazzi, S.4
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43
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0343781234
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University of Pisa Report, DCMN - NT 268(95), Pisa (I), December, OECD-CSNI Report - to be issued
-
D'Auria F., Clement P., Faluomi V., Staedtke H., Vanhoenacker L. (1995) Lesson learned from OECD/CSNI ISP on small break LOCA. University of Pisa Report, DCMN - NT 268(95), Pisa (I), December, OECD-CSNI Report - to be issued
-
(1995)
Lesson Learned from OECD/CSNI ISP on Small Break LOCA
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D'Auria, F.1
Clement, P.2
Faluomi, V.3
Staedtke, H.4
Vanhoenacker, L.5
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44
-
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0041961915
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Natural circulation in CANDU, WWER and PWR type nuclear plants
-
Bologna (I), 22-23 June
-
D'Auria F., Frogheri M., Vigni P. (1995a) Natural Circulation in CANDU, WWER and PWR type Nuclear Plants. 13th Conference of Italian Society of Heat Transport, Bologna (I), 22-23 June.
-
(1995)
13th Conference of Italian Society of Heat Transport
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-
D'Auria, F.1
Frogheri, M.2
Vigni, P.3
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45
-
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0042963675
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Application of the UMAE uncertainty method in assessing the design and the safety of new generation reactors
-
Piacenza (I), 16-19 May
-
D'Auria F., Fruttuoso G., Galassi G.M., Galeazzi S., Oriolo F., Bella L., Cavicchia V., Fiorino E. (1995b) Application of the UMAE uncertainty method in assessing the design and the safety of new generation reactors. IAEA TCM on Progress in Design, Research, Development and Testing of Safety Systems for AWCRs - Piacenza (I), 16-19 May.
-
(1995)
IAEA TCM on Progress in Design, Research, Development and Testing of Safety Systems for AWCRs
-
-
D'Auria, F.1
Fruttuoso, G.2
Galassi, G.M.3
Galeazzi, S.4
Oriolo, F.5
Bella, L.6
Cavicchia, V.7
Fiorino, E.8
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46
-
-
0029426456
-
Bypass of a system code limitation
-
Hilton Head (SC, USA), 13-18 August
-
D'Auria F., Galassi G.M., Giannotti W. (1995c) Bypass of a System Code Limitation. ASME-JSME Fluid Engineering and Laser Anemometry Conference., Hilton Head (SC, USA), 13-18 August.
-
(1995)
ASME-JSME Fluid Engineering and Laser Anemometry Conference
-
-
D'Auria, F.1
Galassi, G.M.2
Giannotti, W.3
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47
-
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3743086130
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Effect of minor boundary conditions on dryout during small LOCA in PWRs
-
Aguas de Lindoia, SP, (BRA), 7-11 August.
-
D'Auria F., Galassi G.M., Madeira A. (1995d) Effect of minor boundary conditions on dryout during small LOCA in PWRs. X Brazilian Meeting on Reactor Physics and Thermalhydraulics, Aguas de Lindoia, SP, (BRA), 7-11 August.
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(1995)
X Brazilian Meeting on Reactor Physics and Thermalhydraulics
-
-
D'Auria, F.1
Galassi, G.M.2
Madeira, A.3
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48
-
-
0006132613
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Current status of methodologies evaluating the uncertainties in the prediction of thermalhydraulic phenomena in nuclear reactors
-
Rome (I), 9-11 October
-
D'Auria F., Leonardi M., Glaeser H., Pochard R. (1995e) Current Status of Methodologies evaluating the Uncertainties in the prediction of thermalhydraulic phenomena in nuclear reactors, International Symp. on Two Phase Flow Modelling and Experimentation - Rome (I), 9-11 October.
-
(1995)
International Symp. on Two Phase Flow Modelling and Experimentation
-
-
D'Auria, F.1
Leonardi, M.2
Glaeser, H.3
Pochard, R.4
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49
-
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0030420512
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Local instability in BWR reactor simulator
-
New Orleans, March
-
D'Auria F., Pellicoro V. (1996) Local instability in BWR reactor simulator. ICONE-4 Conference New Orleans, March.
-
(1996)
ICONE-4 Conference
-
-
D'Auria, F.1
Pellicoro, V.2
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50
-
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0030400942
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Accuracy quantification in SPE-1 to SPE-4 organized by IAEA
-
New Orleans, March
-
D'Auria F., Eramo A., Frogheri M., Galassi G.M. (1996) Accuracy quantification in SPE-1 to SPE-4 organized by IAEA, ICONE-4 Conference, New Orleans, March.
-
(1996)
ICONE-4 Conference
-
-
D'Auria, F.1
Eramo, A.2
Frogheri, M.3
Galassi, G.M.4
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51
-
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0042462511
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-
University of Pisa Report, DCMN - NT 281(96), Pisa (I), July
-
D'Auria F., Fruttuoso G., Galassi G.M., Oriolo F. (1996a) Analysis by Relap5/Mod3.1 code of a DE-CL Breal accident (LB-LOCA) in the EP-1000 plant, University of Pisa Report, DCMN - NT 281(96), Pisa (I), July.
-
(1996)
Analysis by Relap5/mod3.1 Code of a DE-CL Breal Accident (LB-LOCA) in the EP-1000 Plant
-
-
D'Auria, F.1
Fruttuoso, G.2
Galassi, G.M.3
Oriolo, F.4
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52
-
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0030396436
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Comparison between small LOCA scenarios in Eastern and Western type PWRS
-
New Orleans, March
-
D'Auria F., Galassi G.M., Gatta P., Marsili P., Mastrantonio A. (1996b) Comparison between small LOCA scenarios in Eastern and Western type PWRS, ICONE-4 Conference, New Orleans, March.
-
(1996)
ICONE-4 Conference
-
-
D'Auria, F.1
Galassi, G.M.2
Gatta, P.3
Marsili, P.4
Mastrantonio, A.5
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53
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0042462513
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D'auria f
-
de Betou J., Levfert T., Langebuch S., Valtonen K. (to be issued) OECD/CSNI
-
D'Auria F. (Editor), Ambrosini W., Blomstrand J., Anegawa T., In de Betou J., Levfert T., Langebuch S., Valtonen K. (to be issued) State of the Art Report on BWR Stability. OECD/CSNI.
-
State of the Art Report on Bwr Stability
-
-
Ambrosini, W.1
Blomstrand, J.2
Anegawa, T.3
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55
-
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84887047525
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Thermohvdraulics of emergency core cooling in light water reactors - A state-of-the-art report
-
Paris (F), October
-
Lewis M.J., Pochard R., D'Auria F., Karwat H., Wolfert K., Yadigaroglu G., Holmstrom H.L.O. (Lead Authors) (1989) Thermohvdraulics of Emergency Core Cooling in Light Water Reactors - A State-of-the-Art Report CSNI Report no. 161, Paris (F), October.
-
(1989)
CSNI Report No. 161
, vol.161
-
-
Lewis, M.J.1
Pochard, R.2
D'Auria, F.3
Karwat, H.4
Wolfert, K.5
Yadigaroglu, G.6
Holmstrom, H.L.O.7
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56
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0029423107
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Validation exercises of thermalhydraulic system codes for VVER-440/213 type nuclear power plants
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August, FED
-
Szabados L., Ezsol Gy. (1995) Validation exercises of thermalhydraulic system codes for VVER-440/213 type Nuclear Power Plants. ASME-JSME Conference Hilton Head, August, FED Vol. 223.
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(1995)
ASME-JSME Conference Hilton Head
, vol.223
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Szabados, L.1
Ezsol, G.2
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58
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