Validation of the THIRMAL-1 melt-water interaction code

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The THIRMAL-1 computer code has been used to calculate nonexplosive LWR melt-water interactions both in-vessel and ex-vessel. To support the application of the code and enhance its acceptability, THIRMAL-1 has been compared with available data from two of the ongoing FARO experiments at Ispra and two of the Corium Coolant Mixing (CCM) experiments performed at Argonne. THIRMAL-1 calculations for the FARO Scoping Test and Quenching Test 2 as well as the CCM-5 and -6 experiments were found to be in excellent agreement with the experiment results. This lends confidence to the modeling that has been incorporated in the code describing ... continued below

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25 p.

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Chu, C.C.; Sienicki, J.J. & Spencer, B.W. May 1, 1995.

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Description

The THIRMAL-1 computer code has been used to calculate nonexplosive LWR melt-water interactions both in-vessel and ex-vessel. To support the application of the code and enhance its acceptability, THIRMAL-1 has been compared with available data from two of the ongoing FARO experiments at Ispra and two of the Corium Coolant Mixing (CCM) experiments performed at Argonne. THIRMAL-1 calculations for the FARO Scoping Test and Quenching Test 2 as well as the CCM-5 and -6 experiments were found to be in excellent agreement with the experiment results. This lends confidence to the modeling that has been incorporated in the code describing melt stream breakup due to the growth of both Kelvin-Helmholtz and large wave instabilities, the sizes of droplets formed, multiphase flow and heat transfer in the mixing zone surrounding and below the melt stream, as well as hydrogen generation due to oxidation of the melt metallic phase. As part of the analysis of the FARO tests, a mechanistic model was developed to calculate the prefragmentation as it may have occurred when melt relocated from the release vessel to the water surface and the model was compared with the relevant data from FARO.

Physical Description

25 p.

Notes

INIS; OSTI as DE96005219

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  • 7. international topical meeting on nuclear reactor thermal-hydraulics (Nureth-7), Saratoga Springs, NY (United States), 10-15 Sep 1995

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  • Other: DE96005219
  • Report No.: ANL/RE/CP--86472
  • Report No.: CONF-950904--10
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 211541
  • Archival Resource Key: ark:/67531/metadc666468

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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.

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  • May 1, 1995

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  • June 29, 2015, 9:42 p.m.

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  • Dec. 15, 2015, 6:44 p.m.

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Chu, C.C.; Sienicki, J.J. & Spencer, B.W. Validation of the THIRMAL-1 melt-water interaction code, article, May 1, 1995; Illinois. (digital.library.unt.edu/ark:/67531/metadc666468/: accessed October 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.