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2
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0030213085
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DCH dispersal and entrainment experiment in a scaled annular cavity
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M. L. DE BERTODANO, A. BECKER, A. SHARON, and R. SCHNIDER, "DCH Dispersal and Entrainment Experiment in a Scaled Annular Cavity," Nucl. Eng. Des., 164, 271 (1996).
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De Bertodano, M.L.1
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3
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0042539290
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NUREG/CR-6469, SAND96-2289, Sandia National Laboratories
-
T. K. BLANCHAT, M. PILCH, and M. D. ALLEN, "Experiments to Investigate Direct Containment Heating Phenomena with Scaled Models of the Calvert Cliffs Nuclear Power Plant," NUREG/CR-6469, SAND96-2289, Sandia National Laboratories (1997).
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Experiments to Investigate Direct Containment Heating Phenomena with Scaled Models of the Calvert Cliffs Nuclear Power Plant
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Blanchat, T.K.1
Pilch, M.2
Allen, M.D.3
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4
-
-
0012259243
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-
NUREG/CR-5746, SAND99-1634, Sandia National Laboratories
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T. K. BLANCHAT, M. M. PILCH, R. Y. LEE, L. MEYER, and M. PETIT, "Direct Containment Heating Experiments at Low Reactor Coolant System Pressure in the Surtsey Test Facility," NUREG/CR-5746, SAND99-1634, Sandia National Laboratories (1999).
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(1999)
Direct Containment Heating Experiments at Low Reactor Coolant System Pressure in the Surtsey Test Facility
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Blanchat, T.K.1
Pilch, M.M.2
Lee, R.Y.3
Meyer, L.4
Petit, M.5
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5
-
-
0012308204
-
Reactor cavity debris dispersal experiment with simulant at intermediate system pressure
-
Seoul, Korea, August 23-24
-
S. B. KIM, R. J. PARK, H. D. KIM, C. CHEVALL, and M. PETIT, "Reactor Cavity Debris Dispersal Experiment with Simulant at Intermediate System Pressure," presented at SMiRT15 Postconf. Int. Seminar Containment of Nuclear Reactors, Seoul, Korea, August 23-24, 1999.
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(1999)
SMiRT15 Postconf. Int. Seminar Containment of Nuclear Reactors
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-
Kim, S.B.1
Park, R.J.2
Kim, H.D.3
Chevall, C.4
Petit, M.5
-
6
-
-
0012310999
-
Experiments on corium dispersion after lower head failure at moderate pressure
-
Seoul, Korea, August 23-24
-
L. MEYER, G. JACOBS, D. WILHELM, M. GARGALLO, and T. K. BLANCHAT, "Experiments on Corium Dispersion After Lower Head Failure at Moderate Pressure," presented at SMiRT15 Postconf. Int. Seminar Containment of Nuclear Reactors, Seoul, Korea, August 23-24, 1999.
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(1999)
SMiRT15 Postconf. Int. Seminar Containment of Nuclear Reactors
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-
Meyer, L.1
Jacobs, G.2
Wilhelm, D.3
Gargallo, M.4
Blanchat, T.K.5
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7
-
-
0006414824
-
Experiments to investigate the low pressure corium dispersion in EPR geometry
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Karlsruhe, Germany, November 15-18, FZKA 6475, H. ALSMEYER, Ed., Forschungszentrum Karlsruhe
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L. MEYER, "Experiments to Investigate the Low Pressure Corium Dispersion in EPR Geometry," Proc. Organization for Economic Cooperation and Development Workshop Ex-Vessel Debris Coolability, Karlsruhe, Germany, November 15-18, 1999, FZKA 6475, H. ALSMEYER, Ed., Forschungszentrum Karlsruhe (2000).
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(1999)
Proc. Organization for Economic Cooperation and Development Workshop Ex-Vessel Debris Coolability
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-
Meyer, L.1
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8
-
-
0012311001
-
Planned melt dispersal experiments in a scaled cavity
-
Saclay, France, August 25-26
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G. JACOBS and L. MEYER, "Planned Melt Dispersal Experiments in a Scaled Cavity," presented at SMiRT14 Postconf. Int. Seminar Containment of Nuclear Reactors, Saclay, France, August 25-26, 1997.
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(1997)
SMiRT14 Postconf. Int. Seminar Containment of Nuclear Reactors
-
-
Jacobs, G.1
Meyer, L.2
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10
-
-
0032204369
-
An integrated structure and scaling methodology for severe accident technical issue resolution: Development of methodology
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N. ZUBER et al., "An Integrated Structure and Scaling Methodology for Severe Accident Technical Issue Resolution: Development of Methodology," Nucl. Eng. Des., 186, 1 (1998).
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Nucl. Eng. Des.
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, pp. 1
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Zuber, N.1
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13
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0030215178
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A two-cell equilibrium model for predicting direct containment heating
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M. M. PILCH, "A Two-Cell Equilibrium Model for Predicting Direct Containment Heating," Nucl. Eng. Des., 164, 61 (1996).
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Nucl. Eng. Des.
, vol.164
, pp. 61
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Pilch, M.M.1
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14
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0343946284
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Experimental investigation of creep behavior of reactor vessel lower head
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Garching, Germany, March 3-6
-
T. Y. CHU, M. PILCH, J. H. BENTZ, and A. BEHBA-HANI, "Experimental Investigation of Creep Behavior of Reactor Vessel Lower Head," presented at Organization for Economic Cooperation and Development/Committee on the Safety of Nuclear Installations Workshop In-Vessel Core Debris Retention and Coolability, Garching, Germany, March 3-6, 1998.
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(1998)
Organization for Economic Cooperation and Development/Committee on the Safety of Nuclear Installations Workshop In-Vessel Core Debris Retention and Coolability
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Chu, T.Y.1
Pilch, M.2
Bentz, J.H.3
Behba-Hani, A.4
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16
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0347325925
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Distortion of the liquid surface during tank discharge under low g conditions
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D. F. GLUCK, J. P. GILLE, D. J. SIMKIN, and E. E. ZUKOSKI, "Distortion of the Liquid Surface During Tank Discharge Under Low g Conditions," Chem. Eng. Prog. Symp. Ser., No. 61, 62, 150 (1966).
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Chem. Eng. Prog. Symp. Ser., No. 61
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, pp. 150
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Gluck, D.F.1
Gille, J.P.2
Simkin, D.J.3
Zukoski, E.E.4
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17
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0012257833
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-
FZK 6591, Forschungszentrum Karlsruhe (to be published)
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L. MEYER, M. GARGALLO, M. GREULICH, M. KIRST-HALER, M. SCHWALL, G. WÖRNER, and E. WACHTER, "Low Pressure Corium Dispersion Experiments in the DISCO-C Tests Facility with Cold Simulant Fluids," FZK 6591, Forschungszentrum Karlsruhe (to be published).
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Low Pressure Corium Dispersion Experiments in the DISCO-C Tests Facility with Cold Simulant Fluids
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-
Meyer, L.1
Gargallo, M.2
Greulich, M.3
Kirst-Haler, M.4
Schwall, M.5
Wörner, G.6
Wachter, E.7
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18
-
-
0012290010
-
Extrapolation of the thermite dispersion experiment SNL-sup1 to prototypic conditions
-
Albuquerque, New Mexico, August 20-21
-
D. WILHELM, "Extrapolation of the Thermite Dispersion Experiment SNL-Sup1 to Prototypic Conditions," presented at SMiRT16 Postconf. Int. Seminar Containment of Nuclear Reactors, Albuquerque, New Mexico, August 20-21, 2001.
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(2001)
SMiRT16 Postconf. Int. Seminar Containment of Nuclear Reactors
-
-
Wilhelm, D.1
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19
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-
0003669481
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-
P-733, U.S. Atomic Energy Commission
-
Liquid-Metals Handbook, NAVEXOS, P-733, U.S. Atomic Energy Commission (1952).
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(1952)
Liquid-Metals Handbook, NAVEXOS
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