-
1
-
-
0010666673
-
High heat flux nucleate boiling on the outer surface of a heated hemispherical vessel
-
High Heat Flux Nucleate Boiling on the Outer Surface of a Heated Hemispherical Vessel, AICHe Symp. Ser. Vol. 93, No. 314, pp.95-101, 1997
-
(1997)
AICHe Symp. Ser.
, vol.93
, Issue.314
, pp. 95-101
-
-
-
2
-
-
0003786865
-
-
DOE/ID-10460, October
-
Theofanous T.G., Liu C., Additon S., Angelini S,Kymäläinen O., Salmassi T., Invessel Coolability and Retention of a Core Melt, DOE/ID-10460 Vol. 1 and 2, October 1996
-
(1996)
Invessel Coolability and Retention of a Core Melt
, vol.1-2
-
-
Theofanous, T.G.1
Liu, C.2
Additon, S.3
Angelini, S.4
Kymäläinen, O.5
Salmassi, T.6
-
3
-
-
43949175222
-
External cooling of a reactor vessel under severe accident conditions
-
Henry R.E. and Fauske H.K.External Cooling of a Reactor Vessel under Severe Accident Conditions, Nuclear Engineering and Design, 139 (1993), pp. 31-43
-
(1993)
Nuclear Engineering and Design
, vol.139
, pp. 31-43
-
-
Henry, R.E.1
Fauske, H.K.2
-
5
-
-
0031170560
-
Invessel coolability and retention of a core melt
-
Theofanous T.G., Liu C., Additon S., Angelini S.,Kymäläinen O., Salmassi T., Invessel Coolability and Retention of a Core Melt, Nuclear Engineering and Design, 169 (1997), pp. 49-57
-
(1997)
Nuclear Engineering and Design
, vol.169
, pp. 49-57
-
-
Theofanous, T.G.1
Liu, C.2
Additon, S.3
Angelini, S.4
Kymäläinen, O.5
Salmassi, T.6
-
6
-
-
27144523297
-
SULTAN test facility, large scale vessel coolability in natural convection at low pressure
-
Saratoga Springs, NY, USA, Sept. 10-15
-
Rouge S. SULTAN Test Facility, Large Scale Vessel Coolability in Natural Convection at Low Pressure, NURETH-7 Conf., Saratoga Springs, NY, USA, Sept. 10-15, 1995
-
(1995)
NURETH-7 Conf.
-
-
Rouge, S.1
-
7
-
-
84855853542
-
Reactor vessel external cooling for corium retention, SULTAN experimental program and modeling with CATHARE code
-
Garching, Germany, March 3-6
-
Rouge S., Dor I. Geffraye G.Reactor Vessel External Cooling for Corium Retention, SULTAN Experimental Program and Modeling with CATHARE Code, OECD Workshop on IN-Vessel Debris Retention and Coolability, Garching, Germany, March 3-6, 1998
-
(1998)
OECD Workshop on IN-vessel Debris Retention and Coolability
-
-
Rouge, S.1
Dor, I.2
Geffraye, G.3
-
8
-
-
14844326344
-
Critical heat flux through curved, downward facing, thick walls
-
nd, 1994, Pisa, Proc.
-
nd, 1994, Pisa, Proc. Vol. 2, pp. 585-597
-
Int. Conf. on New Trends in Nuclear System Thermohydraulics
, vol.2
, pp. 585-597
-
-
Theofanous, T.G.1
Syri, S.2
Salmassi, T.3
Kymäläinen, O.4
Tuomisto, H.5
-
9
-
-
14844317100
-
The coolability limits of a reactor pressure vessel lower head
-
Saratoga Springs, NY, USA, Sept. 10-15
-
Theofanous T.G. and Syri S.The Coolability Limits of a Reactor Pressure Vessel Lower Head, NURETH-7 Conf., Saratoga Springs, NY, USA, Sept. 10-15, 1995
-
(1995)
NURETH-7 Conf.
-
-
Theofanous, T.G.1
Syri, S.2
-
11
-
-
0031126693
-
A hydrodynamic critical heat flux model for saturated pool boiling on a downward facing curved heating surface
-
Cheung F.B., Haddad K.H.A Hydrodynamic Critical Heat Flux Model for Saturated Pool Boiling on a Downward Facing Curved Heating Surface, Int. J. Heat Transfer, 40 (1997), pp. 1291-1302
-
(1997)
Int. J. Heat Transfer
, vol.40
, pp. 1291-1302
-
-
Cheung, F.B.1
Haddad, K.H.2
-
12
-
-
19044378495
-
Natural convection boiling on the outer surface of a hemispherical vessel surrounded by a thermal insulation structure
-
Garching, May 3-6
-
Cheung F.B., Liu Y.C.Natural Convection Boiling on the Outer Surface of a Hemispherical Vessel Surrounded by a Thermal Insulation Structure, OECD Workshop on In-Vessel Debris Retention and Coolability, Garching, May 3-6, 1998
-
(1998)
OECD Workshop on In-vessel Debris Retention and Coolability
-
-
Cheung, F.B.1
Liu, Y.C.2
-
13
-
-
0345350838
-
Fundamentals of boiling and multiphase flow under extreme conditions
-
Heat Transfer 1998, Kyongju
-
th IHTC, Vol. 1, pp. 131-147, Kyongju, 1998
-
(1998)
th IHTC
, vol.1
, pp. 131-147
-
-
Theofanous, T.G.1
Yuen, W.W.2
-
15
-
-
0003905161
-
Void fraction technology for design and analysis
-
March
-
Chexal et. al. Void Fraction Technology for Design and Analysis, EPRI-Report TR-106326, March 1997
-
(1997)
EPRI-Report
, vol.TR-106326
-
-
Chexal1
-
16
-
-
0001904923
-
The 1995 look-up table for critical heat fluxes in tubes
-
Groeneveld D.C., K. Leung et al.: The 1995 Look-up Table for Critical Heat Fluxes in Tubes. Nuclear Eng. And Design 163 (1996) pp 1-23
-
(1996)
Nuclear Eng. and Design
, vol.163
, pp. 1-23
-
-
Groeneveld, D.C.1
Leung, K.2
-
17
-
-
0347632644
-
The effect of pressure, geometry and the equation of state upon the peak and minimum boiling heat flux
-
Linhard, J.H., Schrock V. E: The Effect of Pressure, Geometry and the Equation of State Upon the Peak and Minimum Boiling heat Flux, J. Heat Transfer, Vol. 85, 1963, pp. 261-272
-
(1963)
J. Heat Transfer
, vol.85
, pp. 261-272
-
-
Linhard, J.H.1
Schrock, V.E.2
-
18
-
-
85007655990
-
On correlating the peak and minimum boiling heat fluxes with pressure and heat configuration
-
Lienhard J. H., Watanabe K.: On Correlating the Peak and Minimum Boiling Heat Fluxes With Pressure and Heat Configuration, J Heat Transfer, Vol. 88, 1966, pp. 94-100
-
(1966)
J Heat Transfer
, vol.88
, pp. 94-100
-
-
Lienhard, J.H.1
Watanabe, K.2
|