Comparisons of TRAC-PF1 calculations with semiscale Mod-3 small-break tests S-07-10D, S-SB-P1, and S-SB-P7. [PWR]

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Semiscale Tests S-07-10D, S-SB-P1, and S-SB-P7 conducted in the Semiscale Mod-3 facility at the Idaho National Engineering Laboratory are analyzed using the latest released version of the Transient Reactor Analysis Code (TRAC-PF1). The results are used to assess TRAC-PF1 predictions of thermal-hydraulic phenomena and the effects of break size and pump operation on system response during slow transients. Test S-07-10D simulated an equivalent pressurized-water-reactor (PWR) 10% communicative cold-leg break for an early pump trip with an emergency core coolant (ECC) injected only into the intact-loop cold leg. Tests S-SB-P1 and S-SB-P7 simulated 2.5% communicative cold-leg breaks for early and late ... continued below

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Pages: 11

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Sahota, M.S. January 1, 1982.

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Semiscale Tests S-07-10D, S-SB-P1, and S-SB-P7 conducted in the Semiscale Mod-3 facility at the Idaho National Engineering Laboratory are analyzed using the latest released version of the Transient Reactor Analysis Code (TRAC-PF1). The results are used to assess TRAC-PF1 predictions of thermal-hydraulic phenomena and the effects of break size and pump operation on system response during slow transients. Test S-07-10D simulated an equivalent pressurized-water-reactor (PWR) 10% communicative cold-leg break for an early pump trip with an emergency core coolant (ECC) injected only into the intact-loop cold leg. Tests S-SB-P1 and S-SB-P7 simulated 2.5% communicative cold-leg breaks for early and late pump trips, respectively, with only high-pressure injection (HPI) into the cold legs. The parameters examined include break flow, primary-system pressure response, primary-system mass distribution, and core characteristics.

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Pages: 11

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NTIS, PC A02/MF A01.

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  • International meeting on thermal nuclear reactor safety, Chicago, IL, USA, 29 Aug 1982

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  • Other: DE82021922
  • Report No.: LA-UR-82-2298
  • Report No.: CONF-820802-14
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 5040552
  • Archival Resource Key: ark:/67531/metadc1059913

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • January 1, 1982

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  • Jan. 22, 2018, 7:23 a.m.

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  • Feb. 1, 2018, 7:01 p.m.

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Sahota, M.S. Comparisons of TRAC-PF1 calculations with semiscale Mod-3 small-break tests S-07-10D, S-SB-P1, and S-SB-P7. [PWR], article, January 1, 1982; New Mexico. (digital.library.unt.edu/ark:/67531/metadc1059913/: accessed December 9, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.