TRAC-PF1/MOD-1 analysis of Loss-Of-Flow Test L9-4

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Los Alamos National Laboratory is developing the Transient Reactor Analysis Code (TRAC) to provide advanced best-estimate predictions of postulated accidents in pressurized water reactors (PWRs) and for many thermal-hydraulic experimental facilities. As part of our independent assessment of code version TRAC-PF1/MOD1, we analyzed Loss-of-Fluid Test (LOFT) L9-4 and compared the test data to the calculated results. This was an anticipated-transient-without-scram test in which the pumps were tripped, the steam generator main feedwater discontinued, and the main steam-outlet valve closed. This data comparison is the first extensive test of TRAC's reactor-kinetics models. The comparisons show that TRAC can calculate the power ... continued below

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Pages: 31

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Meier, J. January 1, 1985.

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Los Alamos National Laboratory is developing the Transient Reactor Analysis Code (TRAC) to provide advanced best-estimate predictions of postulated accidents in pressurized water reactors (PWRs) and for many thermal-hydraulic experimental facilities. As part of our independent assessment of code version TRAC-PF1/MOD1, we analyzed Loss-of-Fluid Test (LOFT) L9-4 and compared the test data to the calculated results. This was an anticipated-transient-without-scram test in which the pumps were tripped, the steam generator main feedwater discontinued, and the main steam-outlet valve closed. This data comparison is the first extensive test of TRAC's reactor-kinetics models. The comparisons show that TRAC can calculate the power generation within a nuclear reactor if the program is supplied with adequate reactor-kinetics input specifications. The data comparisons also indicate that TRAC calculated the thermal-hydraulic parameters within LOFT well with only minor discrepancies. A number of models within TRAC-PF1/MOD1 were verified for the first time. They include the reactor-kinetics models, the trip-activated time-step controls, and the LOFT pump-coastdown calculations. In general, the final input description is adequate to analyze the experiment. The calculations indicate the importance and difficulty of obtaining accurate and applicable reactor-kinetics input data. They also indicate the need to include the effects of xenon-poisoning buildup in the analysis.

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Pages: 31

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NTIS, PC A03/MF A01 - GPO.

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  • 3. international meeting on reactor thermal hydraulics, Newport, RI, USA, 15 Oct 1985

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  • Other: TI85010106
  • Report No.: LA-UR-85-945
  • Report No.: CONF-851007-4
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 5341544
  • Archival Resource Key: ark:/67531/metadc1069934

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  • January 1, 1985

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  • Feb. 4, 2018, 10:51 a.m.

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  • June 4, 2018, 12:48 p.m.

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Meier, J. TRAC-PF1/MOD-1 analysis of Loss-Of-Flow Test L9-4, article, January 1, 1985; New Mexico. (digital.library.unt.edu/ark:/67531/metadc1069934/: accessed June 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.