Actions for Investigation of steam explosion loadings using SIMMER-II [electronic resource].

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Investigation of steam explosion loadings using SIMMER-II [electronic resource].

Published
Los Alamos, N.M. : Los Alamos National Laboratory, 1985.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: 16 : digital, PDF file
Additional Creators
Los Alamos National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
The SIMMER-II computer code was used to estimate the maximum anticipated loads on the upper head of a pressurized water reactor (PWR) following an in-vessel steam explosion. The SIMMER-II equation of state and heat-transfer models were upgraded for this. The modified code was calibrated to Sandia National Laboratories steam explosion data and compared with Los Alamos shallow-pool experiments. A lower-head failure and motion model also was developed. Analysis of parametric cases suggests that the upper bound on the conditional probability of alpha-mode failure, given core melt, should be 0.01 if the vessel upper head and bolts are near normal operating temperatures.
Report Numbers
E 1.99:la-ur-85-4061
E 1.99: conf-8510173-44
conf-8510173-44
la-ur-85-4061
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
01/01/1985.
"la-ur-85-4061"
" conf-8510173-44"
"DE86003658"
13. water reactor safety research information meeting, Gaithersburg, MD, USA, 22 Oct 1985.
Bohl, W.R.
Funding Information
W-7405-ENG-36
View MARC record | catkey: 14369163