Comparisons of Thermal-Hydraulic Phenomena During Isothermal Loss-of-Coolant Experiments and Effect of Scale in LOFT and Semiscale Mod-1: Fid-Bau Portal

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Comparisons of Thermal-Hydraulic Phenomena During Isothermal Loss-of-Coolant Experiments and Effect of Scale in LOFT and Semiscale Mod-1

A. C. Peterson

The thermal-hydraulic phenomena in the Loss-of-Fluid Test (LOFT) and Semiscale Mod-1 facilities during isothermal loss-of-coolant experiments are examined and compared. From these comparisons the effect of scale on the thermal-hydraulic phenomena during isothermal loss-of-coolant experiment transients is assessed. (ERA citation 04:023145)

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Comparisons of Thermal-Hydraulic Phenomena During Isothermal Loss-of-Coolant Experiments and Effect of Scale in LOFT and Semiscale Mod-1

A. C. Peterson

The thermal-hydraulic phenomena in the Loss-of-Fluid Test (LOFT) and Semiscale Mod-1 facilities during isothermal loss-of-coolant experiments are examined and compared. From these comparisons the effect of scale on the thermal-hydraulic phenomena during isothermal loss-of-coolant experiment transients is assessed. (ERA citation 04:023145)

Comparisons of Thermal-Hydraulic Phenomena During Isothermal Loss-of-Coolant Experiments and Effect of Scale in LOFT and Semiscale Mod-1

A. C. Peterson

The thermal-hydraulic phenomena in the Loss-of-Fluid Test (LOFT) and Semiscale Mod-1 facilities during isothermal loss-of-coolant experiments are examined and compared. From these comparisons the effect of scale on the thermal-hydraulic phenomena during isothermal loss-of-coolant experiment transients is assessed. (ERA citation 04:023145)

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Title:

Comparisons of Thermal-Hydraulic Phenomena During Isothermal Loss-of-Coolant Experiments and Effect of Scale in LOFT and Semiscale Mod-1

Contributors:

A. C. Peterson (author)

Publication date:

1978

Size:

61 pages

Type of media:

Report

Type of material:

No indication

Language:

English

Keywords:

Reactor Engineering & Nuclear Power Plants , Loss of coolant , Pwr type reactors , Heat transfer , Hydraulics , Pressure gradients , Reactor safety , Temperature gradients , Nuclear reactor accidents , ERDA/220900 , ERDA/210200 , Scale effect

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