Containment response to postulated ex-vessel core meltdown accidents in the fast flux test facility

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An evaluation of the containment response to ex-vessel core meltdown accidents in the Fast Flux Test Facility is discussed. Particular attention is given to the possibility of the molten fuel/steel mixture remaining in a molten form after entering the reactor cavity. For the molten pool configurations considered, significant H/sub 2/ concentrations were reached in the RCB before the reactor cavity floor was penetrated. The melt-front impacts the pressure transient, not through gas generation, but through penetration into the unlined subcavity resulting in an enhanced sodium-concrete reaction. Hence, if H/sub 2/ recombination is neglected, then steps would have to be taken ... continued below

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Pages: 12

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Pratt, W.T.; Gasser, R.D. & Marchese, A.R. January 1, 1979.

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Description

An evaluation of the containment response to ex-vessel core meltdown accidents in the Fast Flux Test Facility is discussed. Particular attention is given to the possibility of the molten fuel/steel mixture remaining in a molten form after entering the reactor cavity. For the molten pool configurations considered, significant H/sub 2/ concentrations were reached in the RCB before the reactor cavity floor was penetrated. The melt-front impacts the pressure transient, not through gas generation, but through penetration into the unlined subcavity resulting in an enhanced sodium-concrete reaction. Hence, if H/sub 2/ recombination is neglected, then steps would have to be taken to decrease the H/sub 2/ concentration before the RCB design ressure is reached.

Physical Description

Pages: 12

Notes

Dep. NTIS, PC A02/MF A01.

Source

  • International meeting on fast reactor safety technology, Seattle, WA, USA, 19 Aug 1979

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  • Report No.: BNL-NUREG-25522
  • Report No.: CONF-790816-1
  • Grant Number: EY-76-C-02-0016
  • Office of Scientific & Technical Information Report Number: 6200646
  • Archival Resource Key: ark:/67531/metadc1113260

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Office of Scientific & Technical Information Technical Reports

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  • January 1, 1979

Added to The UNT Digital Library

  • Feb. 22, 2018, 7:45 p.m.

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  • March 22, 2018, 4:35 p.m.

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Pratt, W.T.; Gasser, R.D. & Marchese, A.R. Containment response to postulated ex-vessel core meltdown accidents in the fast flux test facility, article, January 1, 1979; United States. (digital.library.unt.edu/ark:/67531/metadc1113260/: accessed July 16, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.