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

Abstract

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.

Authors:
; ;
Publication Date:
Research Org.:
Brookhaven National Lab., Upton, NY (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Project Management
OSTI Identifier:
6200646
Report Number(s):
BNL-NUREG-25522; CONF-790816-1
TRN: 79-016963
DOE Contract Number:  
EY-76-C-02-0016
Resource Type:
Conference
Resource Relation:
Conference: International meeting on fast reactor safety technology, Seattle, WA, USA, 19 Aug 1979
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FFTF REACTOR; CONTAINMENT BUILDINGS; MELTDOWN; CONCRETES; CORIUM; PERFORMANCE; PRESSURE GRADIENTS; REACTOR SAFETY; THERMAL STRESSES; ACCIDENTS; BUILDING MATERIALS; CONTAINMENT; EPITHERMAL REACTORS; FAST REACTORS; LIQUID METAL COOLED REACTORS; MATERIALS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SODIUM COOLED REACTORS; STRESSES; TEST REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 220600 - Nuclear Reactor Technology- Research, Test & Experimental Reactors

Citation Formats

Pratt, W T, Gasser, R D, and Marchese, A R. Containment response to postulated ex-vessel core meltdown accidents in the fast flux test facility. United States: N. p., 1979. Web.
Pratt, W T, Gasser, R D, & Marchese, A R. Containment response to postulated ex-vessel core meltdown accidents in the fast flux test facility. United States.
Pratt, W T, Gasser, R D, and Marchese, A R. 1979. "Containment response to postulated ex-vessel core meltdown accidents in the fast flux test facility". United States. https://www.osti.gov/servlets/purl/6200646.
@article{osti_6200646,
title = {Containment response to postulated ex-vessel core meltdown accidents in the fast flux test facility},
author = {Pratt, W T and Gasser, R D and Marchese, A R},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/6200646}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1979},
month = {1}
}

Conference:
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