B
B.W. Spencer
Researcher at Argonne National Laboratory
Publications - 8
Citations - 191
B.W. Spencer is an academic researcher from Argonne National Laboratory. The author has contributed to research in topics: Containment building & Heat transfer. The author has an hindex of 5, co-authored 8 publications receiving 175 citations.
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Journal ArticleDOI
An integrated structure and scaling methodology for severe accident technical issue resolution: Development of methodology
N. Zuber,G.E. Wilson,Mamoru Ishii,Wolfgang Wulff,B.E. Boyack,A.E Dukler,Peter Griffith,J.M Healzer,R.E Henry,J.R. Lehner,S. Levy,F.J Moody,Martin Pilch,B. R. Sehgal,B.W. Spencer,T.G. Theofanous,J Valente +16 more
TL;DR: The Integrated Structure for Technical Issue Resolution (ISTIR) has been used for severe accident scaling issues as mentioned in this paper, which is a component II of the SASM, and has been tested and demonstrated in a postulated direct containment heating scenario.
Journal ArticleDOI
Ex-vessel melt-coolant interactions in deep water pool: studies and accident management for Swedish BWRs
TL;DR: In Swedish BWRs, the lower drywell beneath the reactor vessel is flooded with water to mitigate against the effects of melt release into the drywell during a severe accident as discussed by the authors, and experiments have also been performed to investigate the benefits of adding surfactants to the water to reduce the likelihood of fine-scale debris formation from steam explosions.
Breakup and quench of molten metal fuel in sodium
TL;DR: In this article, the breakup behavior of kilogram quantities of molten uranium, uranium-zirconium alloy, and uranium-iron alloy pour streams in 600C sodium was studied.
ReportDOI
The probability of containment failure by direct containment heating in surry
Martin Pilch,M. D. Allen,K. D. Bergeron,E. L. Tadios,D. W. Stamps,B.W. Spencer,K. S. Quick,D. L. Knudson +7 more
TL;DR: In a light-water reactor core melt accident, if the reactor pressure vessel (RPV) fails while the reactor coolant system (RCS) at high pressure, the expulsion of molten core debris may pressurize the reactor containment building (RCB) beyond its failure pressure as discussed by the authors.
Journal ArticleDOI
Investigations into the physical phenomena and mechanisms that effect direct containment heating loads
J.L. Binder,B.W. Spencer +1 more
TL;DR: In this paper, the results of integral direct containment heating (DCH) experiments are analyzed and discussed for the insights they have given into understanding the important physical phenomena and mechanisms that effect DCH loads to the containment.