Scoping studies of vapor behavior during a severe accident in a metal-fueled reactor

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Scoping calculations have been performed examining the consequences of fuel melting and pin failures for a reactivity-insertion type accident in a sodium-cooled, pool-type reactor fueled with a metal alloy fuel. The principal gas and vapor species released are shown to be Xe, Cs,and bond sodium contained within the fuel porosity. Fuel vapor pressure is insignificant, and there is no energetic fuel-coolant interaction for the conditions considered. Condensation of sodium vapor as it expands into the upper sodium pool in a jet mixing regime may occur as rapidly as the vapor emerges from the disrupted core (although reactor-material experiments are needed ... continued below

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Pages: 17

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Spencer, B.W. & Marchaterre, J.F. April 15, 1985.

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Description

Scoping calculations have been performed examining the consequences of fuel melting and pin failures for a reactivity-insertion type accident in a sodium-cooled, pool-type reactor fueled with a metal alloy fuel. The principal gas and vapor species released are shown to be Xe, Cs,and bond sodium contained within the fuel porosity. Fuel vapor pressure is insignificant, and there is no energetic fuel-coolant interaction for the conditions considered. Condensation of sodium vapor as it expands into the upper sodium pool in a jet mixing regime may occur as rapidly as the vapor emerges from the disrupted core (although reactor-material experiments are needed to confirm these high condensation rates). If the predictions of rapid direct-contact condensation can be verified experimentally for the sodium system, the implication is that the ability of vapor expansion to perform appreciable work on the system is largely eliminated. Furthermore, the ability of an expanding vapor bubble to transport fuel and fission product species to the cover gas region where they may be released to the containment is also largely eliminated. The radionuclide species except for fission gas are largely retained within the core and sodium pool.

Physical Description

Pages: 17

Notes

NTIS, PC A02/MF A01.

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  • ANS/ENS fast reactor safety meeting, Knoxville, TN, USA, 21 Apr 1985

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  • Other: DE85011474
  • Report No.: CONF-850410-47
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 5745748
  • Archival Resource Key: ark:/67531/metadc1102989

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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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  • April 15, 1985

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  • Feb. 18, 2018, 3:59 p.m.

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  • April 19, 2018, 1:17 p.m.

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Spencer, B.W. & Marchaterre, J.F. Scoping studies of vapor behavior during a severe accident in a metal-fueled reactor, article, April 15, 1985; Illinois. (digital.library.unt.edu/ark:/67531/metadc1102989/: accessed April 26, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.