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          NRC Library  Document Collections  NUREG-Series Publications  Publications Resulting from International AgreementsLOFT Input Dataset Reference Document for RELAP5 Validation Studies (NUREG/IA-0072, AEEW–R2454)

On this page: Publication Information SummaryDownload complete document NUREG/IA-0072 (PDF 2.62 MB)Publication Information **Date Published:** April 1992 **Prepared by:** J. C. Birchley Winfrith Technology Centre United Kingdom Atomic Energy Authority Dorchester, Dorset, DT2 8DH United Kingdom **Prepared as part of:** The Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP) Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Availability Notice Summary Analyses of LOFT experiment data are being carried out in order to validate the RELAP5 computer code for future application to PWR plant analysis. The dataset used in the analyses is based on the latest available information on the LOFT facility issued by the Idaho National Engineering Laboratory (INEL), operators of the LOFT experimental facility. The dataset was developed originally by INEL, for use with RELAP5/MOD1, to support planning and analysis of LOFT experiments. The MOD1 dataset was also used by CEGB Barnwood who subsequently converted the dataset to run with MOD2. The modifications included changes to the nodalisation to take advantage of the crossflow junction option at appropriate locations. Additional pipework representation was introduced for breaks in the intact (or active) loop. Further changes have been made by Winfrith following discussion of calculations performed by the CEGB and Winfrith. These concern the degree of noding in the steam generator, the fluid volume of the steam generator downcomer, and the location of the reactor vessel downcomer bypass path. This document describes the dataset contents relating to the volume, junction, and heat slab data for the intact loop, reactor pressure vessel, broken loop, pressuriser, steam generator secondary, and ECC system. Also described are the control system for steady state initialisation, standard trip settings, and boundary conditions. Reactor Physics Division AEA Technology, Winfrith January 1990 
      
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