Integrated TRAC/MELPROG analyses of a PWR station blackout

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The first complete, coupled, and largely mechanistic analysis of the entire reactor-coolant system during a station blackout (TMLB') core-meltdown accident has been made with MELPROG/TRAC. The calculation was initiated at the start of the transient and ended with a late recovery of cooling. Additional cooling provided by water from the primary system delayed events relative to a standalone MELPROG calculation. Natural circulation within the vessel was established and primary-relief-valve action did little to disturb this flow. In addition, it was calculated directly that the hot leg reached a failure temperature long before vessel failure. Beyond relocation of the core, we ... continued below

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Pages: 20

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Henninger, R. & Dearing, J.F. January 1, 1987.

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Description

The first complete, coupled, and largely mechanistic analysis of the entire reactor-coolant system during a station blackout (TMLB') core-meltdown accident has been made with MELPROG/TRAC. The calculation was initiated at the start of the transient and ended with a late recovery of cooling. Additional cooling provided by water from the primary system delayed events relative to a standalone MELPROG calculation. Natural circulation within the vessel was established and primary-relief-valve action did little to disturb this flow. In addition, it was calculated directly that the hot leg reached a failure temperature long before vessel failure. Beyond relocation of the core, we have calculated the boiloff of the water in the lower head and have estimated the time of vessel failure to be at about 14,700 s into the transient. For ''nominal'' corium-water heat transfer, the boiloff process (steam-production rate) is slow enough that the relief valves prevent pressurization beyond 17.5 MPa. Parametric cases with increased corium-water heat transfer resulted in steaming rates beyond the capability of the relief valves, leading to pressures in excess of 19.2 MPa. Natural convection flow around the loop, if started by removing the water in the loop seal, was blocked by a relatively less-dense hydrogen/steam mixture that flowed to the top of the steam generator. Emergency core-cooling system activation late in the transient (after core slump) resulted in rapid cooling of the periphery of the debris region but slower cooling in the interior regions because of poor water penetration.

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Pages: 20

Notes

NTIS, PC A02/MF A01; 1.

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  • 24. national heat transfer conference and exhibition, Pittsburgh, PA, USA, 9 Aug 1987

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  • Other: DE87005102
  • Report No.: LA-UR-87-167
  • Report No.: CONF-870816-3
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 6174335
  • Archival Resource Key: ark:/67531/metadc1114737

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Office of Scientific & Technical Information Technical Reports

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  • January 1, 1987

Added to The UNT Digital Library

  • Feb. 22, 2018, 7:45 p.m.

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  • May 29, 2018, 6:52 p.m.

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Henninger, R. & Dearing, J.F. Integrated TRAC/MELPROG analyses of a PWR station blackout, article, January 1, 1987; New Mexico. (digital.library.unt.edu/ark:/67531/metadc1114737/: accessed October 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.