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AbstractAbstract
[en] This paper discusses comparisons between pretest predictions performed for Loss-of-Fluid Test (LOFT) Loss-of-Coolant Experiment (LOCE) L3-1 using preliminary versions of RETRAN-02. This project was sponsored by the Electric Power Research Institute to assess the applicability of the loss-of-fluid test (LOFT) experimental test results to large pressurized water reactor behavior during postulatd accidents and to validate the abiity of thermal hydraulic codes such as RETRAN to describe accurately reactor behavior during apostulated loss-of-coolant accident (LOCA). An integral part of this project was an evaluation of the adequacey of the LOFT data. The LOFT data were reviewed from the viewpoints of understanding the accident behavior of pressurized water reactors (PWRs) and to evaluate the consistency, accuracy, and completeness of the experimental data for code assessment purposes
Original Title
PWR
Primary Subject
Source
Agee, L.J. (ed.); Electric Power Research Inst., Palo Alto, CA (USA); p. 7.1-7.15; Apr 1981; p. 7.1-7.15; 1. international RETRAN conference; Seattle, WA, USA; 22 - 24 Sep 1980
Record Type
Report
Literature Type
Conference
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