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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
B. Tourniaire, O. Varo
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 143-151
Technical Note | Icapp '06 | doi.org/10.13182/NT164-143
Articles are hosted by Taylor and Francis Online.
In case of a pressurized water reactor's severe accident with core meltdown and vessel failure, corium would spread on the concrete basemat of the plant. The high temperature of the corium pool maintained by the residual power would lead to the erosion of the concrete walls and potentially to the bypass of the containment. The ablation velocity of concrete is governed by the heat flux between the corium pool and the concrete wall, and its calculation is of particular significance to predict whether and when the basemat would fail in such a situation. From a hydrodynamic point of view, this issue is related to heat transfer between a volumetric heated bubbling pool and a porous wall with gas injection. Several experimental studies have been performed in the past, and many correlations have been proposed to address this issue. The main purpose of this paper is to assess these correlations from comparisons against the available experimental data. After a review of these data, the different correlations are presented. Attention focuses here on the correlations generally used in molten core-concrete interaction study: The Kutateladze-Malenkov, Konsetov, and BALI correlations. Deckwer's correlation is also included in this review. The comparisons between the results of these correlations and the experimental data are then discussed.