Evaluation of EBR-II driver-fuel elements following an unprotected station blackout accident

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One of the current design objectives for a liquid metal reactor (LMR) is the inherent shutdown-cooling capability of the reactor, such that the reactor itself can safely reduce power following a total loss of pump power without activating the reactor shutdown system (RSS). Following a loss-of-flow (LOF) accident and a failure of RSS, in EBR-II, reactor core damage and plant restartability is of considerable interest. In the LOF event, high temperature in the reactor causes negative reactivity feedback that reduces reactor power. After an accident, reactor fuel performance is one of the factors used to assess the restartability of the ... continued below

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Pages: 17

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Chang, L.K. & Bottcher, J.H. January 1, 1986.

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Description

One of the current design objectives for a liquid metal reactor (LMR) is the inherent shutdown-cooling capability of the reactor, such that the reactor itself can safely reduce power following a total loss of pump power without activating the reactor shutdown system (RSS). Following a loss-of-flow (LOF) accident and a failure of RSS, in EBR-II, reactor core damage and plant restartability is of considerable interest. In the LOF event, high temperature in the reactor causes negative reactivity feedback that reduces reactor power. After an accident, reactor fuel performance is one of the factors used to assess the restartability of the plant. A thermal-hydraulic-neutronic analysis was performed to determine the response of the plant and the temperature of individual subassemblies. These temperatures were then used to assess the damage to driver fuel elements caused by the station blackout accident. The maximum depth of cladding wastage from molten eutectic at temperatures >715/sup 0/C was found to be 0.0053 mm for the hottest subassembly; this value is considerably less than the 0.28 mm cladding thickness. 12 refs.

Physical Description

Pages: 17

Notes

NTIS, PC A02/MF A01.

Source

  • 6. power plant dynamics, control and testing symposium, Knoxville, TN, USA, 14 Apr 1986

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  • Other: DE86006453
  • Report No.: CONF-860414-1
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 6143275
  • Archival Resource Key: ark:/67531/metadc1113608

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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, 1986

Added to The UNT Digital Library

  • Feb. 22, 2018, 7:45 p.m.

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  • April 18, 2018, 6:45 p.m.

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Chang, L.K. & Bottcher, J.H. Evaluation of EBR-II driver-fuel elements following an unprotected station blackout accident, article, January 1, 1986; Illinois. (digital.library.unt.edu/ark:/67531/metadc1113608/: accessed April 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.