Actions for Assessment of a core meltdown in the gas-cooled fast breeder reactor with an upflow core [electronic resource].

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Assessment of a core meltdown in the gas-cooled fast breeder reactor with an upflow core [electronic resource].

Published
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1979.
Physical Description
Pages: 18 : digital, PDF file
Additional Creators
United States. Department of Energy. Office of Scientific and Technical Information
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Summary
This paper discusses the chronological sequence of events and supporting analysis of a postulated total loss of all coolant circulation in the gas-cooled fast breeder reactor (GCFR) with an upflow core. Redundant and diverse cooling systems are provided for decay heat removal, including pressurized natural circulation in the core auxiliary cooling system, which reduce the probability of this postulated event below the range of plant design bases. Nevertheless, this postulated accident has been considered so that the potential for consequence mitigation and containment margin could be investigated. Two distinct phases of the sequence are discussed: (1) the core response to a total loss of forced and natural coolant circulation and (2) the capability of the prestressed concrete reactor vessel (PCRV) to retain molten fuel debris. Specific design features of the GCFR which prevent recriticality and fuel vaporization due to fuel slumping are under investigation. Analytical work has been initiated to determine the potential for consequence mitigation in the PCRV and the containment. Several concepts for postaccident fuel containment have been identified and appear technically feasible.
Report Numbers
E 1.99:ga-a-15520
ga-a-15520
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Note
Published through SciTech Connect.
07/01/1979.
"ga-a-15520"
Frank, M.V.; Kang, C.; Torri, A.
General Atomic Co., San Diego, CA (USA)
Funding Information
AT03-76SF71023
View MARC record | catkey: 14369525