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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Michael D. Allen, Martin M. Pilch, Richard O. Griffith, Robert T. Nichols
Nuclear Technology | Volume 100 | Number 1 | October 1992 | Pages 52-69
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34753
Articles are hosted by Taylor and Francis Online.
The limited flight path experiments investigate the effect of reactor subcompartment flight path length on direct containment heating (DCH) in a severe reactor accident. The test series consists of eight experiments with nominal flight paths of 1, 2, or 8 m. A thermitically generated mixture of iron, chromium, and alumina simulates the corium melt of a severe accident in a light water reactor. After thermite ignition, superheated steam forcibly ejects the molten debris into a 1:10 linear scale model of either the Surry or Zion reactor cavity. The blowdown steam entrains the molten debris and disperses it into a 103-m3 containment model. The vessel pressure, gas temperature, debris temperature, hydrogen produced by steam/metal reactions, debris velocity, mass dispersed into the Surtsey vessel, and debris particle size are measured for each experiment. The measured peak pressure for each experiment is normalized by the total amount of energy introduced into the Surtsey vessel and increases with lengthened flight path. The debris temperature at the cavity exit is ∼2320 K. Gas grab samples indicate that steam in the cavity reacts rapidly to form hydrogen, so the driving gas is a mixture of steam and hydrogen. In these experiments, ∼70% of the steam driving gas is converted to hydrogen. These experiments indicate that the bulk of DCH interactions occur below the subcompartment structure, not in the upper dome of Surtsey. The effect of deentrainment by reactor subcompartments may significantly reduce the peak containment load in a severe reactor accident.