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Comparisons of RELAP4/MOD6 to LOFT and Semiscale Isothermal Data

T. D. Knight / C. J. Bliem

The results are presented of the independent assessment studies of the RELAP4/MOD6 computer code utilizing LOFT and Semiscale system models to analyze isothermal blowdowns. RELAP4 calculations are compared to data from LOFT Test L1-4 and from Semiscale Test S-01-4A, the counterpart test to L1-4. The isothermal experiments provide a test of the RELAP4 hydraulic model in which the heat transfer effects are minimized. Deficiencies in the comparisons are noted, and improved modeling techniques recommended. (ERA citation 04:026544)

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Comparisons of RELAP4/MOD6 to LOFT and Semiscale Isothermal Data

T. D. Knight / C. J. Bliem

The results are presented of the independent assessment studies of the RELAP4/MOD6 computer code utilizing LOFT and Semiscale system models to analyze isothermal blowdowns. RELAP4 calculations are compared to data from LOFT Test L1-4 and from Semiscale Test S-01-4A, the counterpart test to L1-4. The isothermal experiments provide a test of the RELAP4 hydraulic model in which the heat transfer effects are minimized. Deficiencies in the comparisons are noted, and improved modeling techniques recommended. (ERA citation 04:026544)

Comparisons of RELAP4/MOD6 to LOFT and Semiscale Isothermal Data

T. D. Knight / C. J. Bliem

The results are presented of the independent assessment studies of the RELAP4/MOD6 computer code utilizing LOFT and Semiscale system models to analyze isothermal blowdowns. RELAP4 calculations are compared to data from LOFT Test L1-4 and from Semiscale Test S-01-4A, the counterpart test to L1-4. The isothermal experiments provide a test of the RELAP4 hydraulic model in which the heat transfer effects are minimized. Deficiencies in the comparisons are noted, and improved modeling techniques recommended. (ERA citation 04:026544)

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Title:

Comparisons of RELAP4/MOD6 to LOFT and Semiscale Isothermal Data

Contributors:

T. D. Knight (author) / C. J. Bliem (author)

Publication date:

1978

Size:

65 pages

Type of media:

Report

Type of material:

No indication

Language:

English

Keywords:

Reactor Engineering & Nuclear Power Plants , Loss of coolant , Pwr type reactors , Blowdown , Computer calculations , Fluid flow , Hydraulics , Mathematical models , Pressure gradients , ERDA/220900 , ERDA/210200 , RELAP4/MOD6 computer program

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