-
1
-
-
79952969914
-
Overview on PANDA test facility and ISP-42 tests data base
-
IAEA-TECDOC-1474
-
Aksan, N.; 2005. Overview on PANDA test facility and ISP-42 tests data base. In: Natural Circulation in Water Cooled Power Plants, IAEA-TECDOC-1474, pp. 415-431.
-
(2005)
Natural Circulation in Water Cooled Power Plants
, pp. 415-431
-
-
Aksan, N.1
-
2
-
-
33645808665
-
On various forms of the heat and mass transfer analogy: Discussion and application to condensation experiments
-
W. Ambrosini, N. Forgione, A. Manfredini, and F. Oriolo On various forms of the heat and mass transfer analogy: Discussion and application to condensation experiments Nucl. Eng. Des. 236 2006 1013 1027
-
(2006)
Nucl. Eng. Des.
, vol.236
, pp. 1013-1027
-
-
Ambrosini, W.1
Forgione, N.2
Manfredini, A.3
Oriolo, F.4
-
3
-
-
0032179015
-
Experimental analysis of heat transfer within the AP600 containment under postulated accident conditions
-
PII S0029549398002325
-
M.H. Anderson, L.E. Herranz, and M.L. Corradini Experimental analysis of heat transfer within the AP600 containment under postulated accident conditions Nucl. Eng. Des. 185 1998 153 172 (Pubitemid 128410521)
-
(1998)
Nuclear Engineering and Design
, vol.185
, Issue.2-3
, pp. 153-172
-
-
Anderson, M.H.1
Herranz, L.E.2
Corradini, M.L.3
-
4
-
-
2342475184
-
The design and safety features of the IRIS reactor
-
M.D. Carelli, L.E. Conway, L. Oriani, B. Petrović, C.V. Lombardi, M.E. Ricotti, A.C.O. Barroso, J.M. Collado, L. Cinotti, N.E. Todreas, D. Grgić, M.M. Moraes, R.D. Boroughs, H. Ninokata, D.T. Ingersoll, and F. Oriolo The design and safety features of the IRIS reactor Nucl. Eng. Des. 230 2004 151 167
-
(2004)
Nucl. Eng. Des.
, vol.230
, pp. 151-167
-
-
Carelli, M.D.1
Conway, L.E.2
Oriani, L.3
Petrović, B.4
Lombardi, C.V.5
Ricotti, M.E.6
Barroso, A.C.O.7
Collado, J.M.8
Cinotti, L.9
Todreas, N.E.10
Grgić, D.11
Moraes, M.M.12
Boroughs, R.D.13
Ninokata, H.14
Ingersoll, D.T.15
Oriolo, F.16
-
5
-
-
79951671148
-
-
10.1155/2009/579430 Article ID 579430
-
M. Carelli, L. Conway, M. Dzodzo, A. Maioli, L. Oriani, G. Storrick, B. Petrović, A. Achilli, G. Cattadori, C. Congiu, R. Ferri, M. Ricotti, D. Papini, F. Bianchi, P. Meloni, S. Monti, F. Berra, D. Grgić, G. Yoder, and A. Alemberti The SPES3 Experimental Facility Design for the IRIS Reactor Simulation. Science and Technology of Nuclear Installations, vol. 2009 2009 10.1155/2009/579430 Article ID 579430, 12pp
-
(2009)
The SPES3 Experimental Facility Design for the IRIS Reactor Simulation. Science and Technology of Nuclear Installations
, vol.2009
-
-
Carelli, M.1
Conway, L.2
Dzodzo, M.3
Maioli, A.4
Oriani, L.5
Storrick, G.6
Petrović, B.7
Achilli, A.8
Cattadori, G.9
Congiu, C.10
Ferri, R.11
Ricotti, M.12
Papini, D.13
Bianchi, F.14
Meloni, P.15
Monti, S.16
Berra, F.17
Grgić, D.18
Yoder, G.19
Alemberti, A.20
more..
-
8
-
-
79953237903
-
Integrated analysis for a small break LOCA in the IRIS reactor using MELCOR and RELAP5 codes
-
Dubrovnik, Croatia
-
A. Del Nevo, A. Manfredini, F. Oriolo, S. Paci, and L. Oriani Integrated analysis for a small break LOCA in the IRIS reactor using MELCOR and RELAP5 codes Proc. 5th Int. Conf. on Nuclear Option in Countries with Small and Medium Electricity Grids Dubrovnik, Croatia 2004
-
(2004)
Proc. 5th Int. Conf. on Nuclear Option in Countries with Small and Medium Electricity Grids
-
-
Del Nevo, A.1
Manfredini, A.2
Oriolo, F.3
Paci, S.4
Oriani, L.5
-
10
-
-
84855326812
-
SPES3-IRIS facility nodalization for RELAP5 Mod. 3.3 code and steady state qualification
-
January 2009
-
Ferri, R.; Congiu, C.; January 2009. SPES3-IRIS facility nodalization for RELAP5 Mod. 3.3 code and steady state qualification. SIET 01 423 RT 08 Rev.0.
-
SIET 01 423 RT 08 Rev.0.
-
-
Ferri, R.1
Congiu, C.2
-
11
-
-
48349141166
-
Theoretical modeling of condensation of steam outside different vertical geometries (tube, flat plates) in the presence of noncondensable gases like air and helium
-
A. Ganguli, A.G. Patel, N.K. Maheshwari, and A.B. Pandit Theoretical modeling of condensation of steam outside different vertical geometries (tube, flat plates) in the presence of noncondensable gases like air and helium Nucl. Eng. Des. 238 2008 2328 2340
-
(2008)
Nucl. Eng. Des.
, vol.238
, pp. 2328-2340
-
-
Ganguli, A.1
Patel, A.G.2
Maheshwari, N.K.3
Pandit, A.B.4
-
12
-
-
0029208548
-
Two-fluid modeling of the condensation in the presence of noncondensable in two-phase flows
-
S.M. Ghiaasiaan, B.K. Kamboj, and S.I. Abdel-Khalik Two-fluid modeling of the condensation in the presence of noncondensable in two-phase flows Nucl. Sci. Eng. 119 1995 1 17
-
(1995)
Nucl. Sci. Eng.
, vol.119
, pp. 1-17
-
-
Ghiaasiaan, S.M.1
Kamboj, B.K.2
Abdel-Khalik, S.I.3
-
14
-
-
0029852651
-
An overview of the primary parameters and methods for determining condensation heat transfer to containment structures
-
J. Green, and K. Almenas An overview of the primary parameters and methods for determining condensation heat transfer to containment structures Nucl. Saf. 37 1 1996 26 47
-
(1996)
Nucl. Saf.
, vol.37
, Issue.1
, pp. 26-47
-
-
Green, J.1
Almenas, K.2
-
16
-
-
0005379123
-
Heat transfer modeling in the vertical tubes of the passive containment cooling system of the simplified boiling water reactor
-
PII S0029549397001787
-
L.E. Herranz, J.L. Muñoz-Cobo, and G. Verdú Heat transfer modeling in the vertical tubes of the passive containment cooling system of the simplified boiling water reactor Nucl. Eng. Des. 178 1997 29 44 (Pubitemid 127433770)
-
(1997)
Nuclear Engineering and Design
, vol.178
, Issue.1
, pp. 29-44
-
-
Herranz, L.E.1
Munoz-Cobo, J.L.2
Verdu, G.3
-
17
-
-
0032115788
-
A diffusion layer model for steam condensation within the AP600 containment
-
PII S0029549398001642
-
L.E. Herranz, M.H. Anderson, and M.L. Corradini A diffusion layer model for steam condensation within the AP600 containment Nucl. Eng. Des. 183 1998 133 150 (Pubitemid 128420628)
-
(1998)
Nuclear Engineering and Design
, vol.183
, Issue.1-2
, pp. 133-150
-
-
Herranz, L.E.1
Anderson, M.H.2
Corradini, M.L.3
-
18
-
-
0342801600
-
Advanced PWR passive containment cooling system testing
-
Pittsburgh, PA, USA
-
M.D. Kennedy, F.E. Peters, M.D. Carelli, and A.T. Pieczynski Advanced PWR passive containment cooling system testing Proc. ARS'94 Int. Top. Meet. On Advanced Reactor Safety, vol. 1 Pittsburgh, PA, USA 1994 pp. 249-256
-
(1994)
Proc. ARS'94 Int. Top. Meet. on Advanced Reactor Safety, Vol. 1
-
-
Kennedy, M.D.1
Peters, F.E.2
Carelli, M.D.3
Pieczynski, A.T.4
-
19
-
-
0007564460
-
Modeling of condensation heat transfer in a reactor containment
-
M.H. Kim, and M.L. Corradini Modeling of condensation heat transfer in a reactor containment Nucl. Eng. Des. 118 1990 193 212
-
(1990)
Nucl. Eng. Des.
, vol.118
, pp. 193-212
-
-
Kim, M.H.1
Corradini, M.L.2
-
20
-
-
0002523296
-
An investigation of condensation from steam-gas mixtures flowing downward inside a vertical tube
-
PII S0029549397001854
-
S.Z. Kuhn, V.E. Schrock, and P.F. Peterson An investigation of condensation from steam-gas mixtures flowing downward inside a vertical tube Nucl. Eng. Des. 177 1997 53 69 (Pubitemid 127434728)
-
(1997)
Nuclear Engineering and Design
, vol.177
, Issue.1-3
, pp. 53-69
-
-
Kuhn, S.Z.1
Schrock, V.E.2
Peterson, P.F.3
-
21
-
-
33846934169
-
Iris small break loca phenomena identification and ranking table (PIRT)
-
DOI 10.1016/j.nucengdes.2006.09.028, PII S0029549306005528
-
T.K. Larson, F.J. Moody, G.E. Wilson, W.L. Brown, C. Frepoli, J. Hartz, B.G. Woods, and L. Oriani IRIS small break LOCA phenomena identification and ranking table (PIRT) Nucl. Eng. Des. 237 2007 618 626 (Pubitemid 46241244)
-
(2007)
Nuclear Engineering and Design
, vol.237
, Issue.6
, pp. 618-626
-
-
Larson, T.K.1
Moody, F.J.2
Wilson, G.E.3
Brown, W.L.4
Frepoli, C.5
Hartz, J.6
Woods, B.G.7
Oriani, L.8
-
22
-
-
2642566991
-
IRIS Safety Features and Analysis of Non-LOCA Transients and Accidents
-
New Orleans, Louisiana, USA
-
L. Oriani, L.E. Conway, D. Grgić, N. Čavlina, F. Berra, M. Ricotti, G. Ambrogi, and F. Oriolo IRIS Safety Features and Analysis of Non-LOCA Transients and Accidents Proc. ANS/ENS Int. Meet. GLOBAL 2003 New Orleans, Louisiana, USA 2003
-
(2003)
Proc. ANS/ENS Int. Meet. GLOBAL 2003
-
-
Oriani, L.1
Conway, L.E.2
Grgić, D.3
Čavlina, N.4
Berra, F.5
Ricotti, M.6
Ambrogi, G.7
Oriolo, F.8
-
25
-
-
0027439486
-
Diffusion layer theory for turbulent vapour condensation with non-condensable gases
-
P.F. Peterson, V.E. Schrock, and T. Kageyama Diffusion layer theory for turbulent vapour condensation with non-condensable gases J. Heat Transf. 115 1993 998 1003
-
(1993)
J. Heat Transf.
, vol.115
, pp. 998-1003
-
-
Peterson, P.F.1
Schrock, V.E.2
Kageyama, T.3
-
26
-
-
0000434790
-
Theoretical basis for the Uchida correlation for condensation in reactor containments
-
P.F. Peterson Theoretical basis for the Uchida correlation for condensation in reactor containments Nucl. Eng. Des. 162 1996 301 306
-
(1996)
Nucl. Eng. Des.
, vol.162
, pp. 301-306
-
-
Peterson, P.F.1
-
27
-
-
79953250264
-
-
October 2001 Dipartimento Di Ingegneria Meccanica, Nucleare E Della Produzione, Università di Pisa, Pisa, DIMNP NT 451 (01).
-
Petruzzi, A.; D'Auria, F.; Galassi, G.M.; October 2001. Analysis of OECD/CSNI ISP-42 PANDA Experiment by RELAP5/Mod3.2 Code. Dipartimento Di Ingegneria Meccanica, Nucleare E Della Produzione, Universit di Pisa, Pisa, DIMNP NT 451 (01).
-
Analysis of OECD/CSNI ISP-42 PANDA Experiment by RELAP5/Mod3.2 Code
-
-
Petruzzi, A.1
D'Auria, F.2
Galassi, G.M.3
-
29
-
-
33845395162
-
Variations of a passive safety containment for a BWR with active and passive safety systems
-
DOI 10.1016/j.nucengdes.2006.08.009, PII S002954930600478X
-
T. Sato, and Y. Kojima Variations of a passive safety containment for a BWR with active and passive safety systems Nucl. Eng. Des. 237 2007 74 86 (Pubitemid 44908407)
-
(2007)
Nuclear Engineering and Design
, vol.237
, Issue.1
, pp. 74-86
-
-
Sato, T.1
Kojima, Y.2
-
30
-
-
0347282594
-
Thermal/hydraulic challenges for the SBWR
-
Salt Lake City, UT, USA
-
C. Sawyer Thermal/hydraulic challenges for the SBWR Proc. 5th Int. Top. Meet. on Reactor Thermal-Hydraulics, NURETH-5 'Towards the Next Generation of Nuclear Power Reactors', vol. 1 Salt Lake City, UT, USA 1992 21 24
-
(1992)
Proc. 5th Int. Top. Meet. on Reactor Thermal-Hydraulics, NURETH-5 'Towards the Next Generation of Nuclear Power Reactors', Vol. 1
, pp. 21-24
-
-
Sawyer, C.1
-
31
-
-
33745224696
-
Westinghouse AP1000 advanced passive plant
-
T.L. Schulz Westinghouse AP1000 advanced passive plant Nucl. Eng. Des. 236 2006 1547 1557
-
(2006)
Nucl. Eng. Des.
, vol.236
, pp. 1547-1557
-
-
Schulz, T.L.1
-
32
-
-
0027607702
-
Local heat transfer coefficients for forced-convection condensation of steam in a vertical tube in the presence of a noncondensable gas
-
M. Siddique, M.W. Golay, and M.S. Kazimi Local heat transfer coefficients for forced-convection condensation of steam in a vertical tube in the presence of a noncondensable gas Nucl. Technol. 102 1993 386 402
-
(1993)
Nucl. Technol.
, vol.102
, pp. 386-402
-
-
Siddique, M.1
Golay, M.W.2
Kazimi, M.S.3
-
33
-
-
85004558913
-
Condensation heat transfer in the presence of a noncondensable gas
-
E.M. Sparrow, and S.H. Lin Condensation heat transfer in the presence of a noncondensable gas J. Heat Transf. 86 1964 430 436
-
(1964)
J. Heat Transf.
, vol.86
, pp. 430-436
-
-
Sparrow, E.M.1
Lin, S.H.2
-
34
-
-
0347282715
-
Westinghouse-Gothic comparison with passive containment cooling system tests scaling evaluation and analysis
-
D.R. Spencer, J. Woodcock, O.F. Wright, and J.A. Gresham Westinghouse-Gothic comparison with passive containment cooling system tests scaling evaluation and analysis Proc. 2nd ASME/JSME Nuclear Engineering Joint Conf.; San Francisco, CA, USA 1993
-
(1993)
Proc. 2nd ASME/JSME Nuclear Engineering Joint Conf.; San Francisco, CA, USA
-
-
Spencer, D.R.1
Woodcock, J.2
Wright, O.F.3
Gresham, J.A.4
-
35
-
-
0005415925
-
Evaluation of post-incident cooling systems of light-water power reactors, vol. 13
-
Geneva, Switzerland
-
H. Uchida, A. Oyama, and Y. Togo Evaluation of post-incident cooling systems of light-water power reactors, vol. 13 Proc. 3rd Int. Conf. on the Peaceful Uses of Atomic Energy Geneva, Switzerland 1965 93 102
-
(1965)
Proc. 3rd Int. Conf. on the Peaceful Uses of Atomic Energy
, pp. 93-102
-
-
Uchida, H.1
Oyama, A.2
Togo, Y.3
-
36
-
-
79953236991
-
-
U.S. NRC Nuclear Safety Analysis Division, December 2001. RELAP5/MOD3.3 Code Manual. NUREG/CR-5535/Rev 1.
-
U.S. NRC Nuclear Safety Analysis Division, December 2001. RELAP5/MOD3.3 Code Manual. NUREG/CR-5535/Rev 1.
-
-
-
-
38
-
-
0000834995
-
Condensation in a natural circulation loop with a noncondensable gas present
-
Tsukuba, Japan
-
K.M. Vierow, and V.E. Schrock Condensation in a natural circulation loop with a noncondensable gas present Proc. Int. Conf. on Multiphase Flows '91 Tsukuba, Japan 1991 183 186
-
(1991)
Proc. Int. Conf. on Multiphase Flows '91
, pp. 183-186
-
-
Vierow, K.M.1
Schrock, V.E.2
-
39
-
-
0009778950
-
Numerical modeling of condensation from vapor-gas mixtures for the forced downflow inside a tube
-
Saratoga Springs, NY, USA
-
R.Y. Yuann, V.E. Schrock, and X.M. Chen Numerical modeling of condensation from vapor-gas mixtures for the forced downflow inside a tube Proc. 7th Int. Top. Meet. on Reactor Thermal-Hydraulics, NURETH-7 Saratoga Springs, NY, USA 1995 377 401
-
(1995)
Proc. 7th Int. Top. Meet. on Reactor Thermal-Hydraulics, NURETH-7
, pp. 377-401
-
-
Yuann, R.Y.1
Schrock, V.E.2
Chen, X.M.3
|