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Refinado por: assunto: Nuclear Reactor Technology remover
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1
Cross-sectional void fraction distribution measurements in a vertical annulus two-phase flow by high speed X-ray computed tomography and real-time neutron radiography techniques
Cross-sectional void fraction distribution measurements in a vertical annulus two-phase flow by high speed X-ray computed tomography and real-time neutron radiography techniques
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Cross-sectional void fraction distribution measurements in a vertical annulus two-phase flow by high speed X-ray computed tomography and real-time neutron radiography techniques

Harvel, G.D. ; Hori, K. ; Kawanishi, K. ; Chang, J.S.

Flow measurement and instrumentation, 1999-12, Vol.10 (4), p.259-266 [Periódico revisado por pares]

United States: Elsevier Ltd

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2
On heat transfer characteristics of real and simulant melt pool experiments
On heat transfer characteristics of real and simulant melt pool experiments
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On heat transfer characteristics of real and simulant melt pool experiments

Dinh, T.N. ; Nourgaliev, R.R. ; Sehgal, B.R.

Nuclear engineering and design, 1997-06, Vol.169 (1), p.151-164 [Periódico revisado por pares]

United States: Elsevier B.V

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3
Numerical simulation of multi-dimensional two-phase flow based on flux vector splitting
Numerical simulation of multi-dimensional two-phase flow based on flux vector splitting
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Numerical simulation of multi-dimensional two-phase flow based on flux vector splitting

Städtke, H. ; Franchello, G. ; Worth, B.

Nuclear engineering and design, 1997-12, Vol.177 (1), p.199-213 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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4
A comparison of critical heat flux in tubes and bilaterally heated annuli
A comparison of critical heat flux in tubes and bilaterally heated annuli
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A comparison of critical heat flux in tubes and bilaterally heated annuli

Doerffer, S ; Groeneveld, D.C ; Cheng, S.C

Nuclear engineering and design, 1997-12, Vol.177 (1), p.105-120 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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5
Numerical boron mixing studies for Loviisa nuclear power plant
Numerical boron mixing studies for Loviisa nuclear power plant
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Numerical boron mixing studies for Loviisa nuclear power plant

Gango, Peter

Nuclear engineering and design, 1997-12, Vol.177 (1), p.239-254 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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6
Boiling characteristics of dilute polymer solutions and implications for the suppression of vapor explosions
Boiling characteristics of dilute polymer solutions and implications for the suppression of vapor explosions
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Boiling characteristics of dilute polymer solutions and implications for the suppression of vapor explosions

Bang, K.H ; Kim, M.H ; Jeun, G.D

Nuclear engineering and design, 1997-12, Vol.177 (1), p.255-264 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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7
Analysis of steam generator loss-of-feedwater experiments with APROS and RELAP5/MOD3.1 computer codes
Analysis of steam generator loss-of-feedwater experiments with APROS and RELAP5/MOD3.1 computer codes
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Analysis of steam generator loss-of-feedwater experiments with APROS and RELAP5/MOD3.1 computer codes

Virtanen, E ; Haapalehto, T ; Kouhia, J

Nuclear engineering and design, 1997-12, Vol.177 (1), p.147-153 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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8
Analysis of the return to power scenario following a LBLOCA in a PWR
Analysis of the return to power scenario following a LBLOCA in a PWR
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Analysis of the return to power scenario following a LBLOCA in a PWR

Macian, Rafael ; Tyler, Trevor N ; Mahaffy, John H

Nuclear engineering and design, 1997-12, Vol.177 (1), p.189-197 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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9
Two-Phase Velocity Measurements around Cylinders Using Particle Image Velocimetry
Two-Phase Velocity Measurements around Cylinders Using Particle Image Velocimetry
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Two-Phase Velocity Measurements around Cylinders Using Particle Image Velocimetry

Hassan, Y.A. ; Philip, O.G. ; Schmidl, W.D.

Multiphase Flow 1995, 1995, p.759-769

Elsevier B.V

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