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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
Karsten Fischer
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 58-62
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A15851
Articles are hosted by Taylor and Francis Online.
The advantage of passive catalytic modules for hydrogen mitigation during core-melt accidents, as compared with active devices like forced-flow recombiners or ignitors, is given by the higher reliability of operation and the elimination of potentially violent combustion events. An important step in the qualification of a passive catalytic module system is the determination of the total required capacity and its distribution at various locations in the containment. Experiments and analytic modeling work were performed to qualify the installation of a system of catalytic modules for a large dry pressurized water reactor (PWR) containment. The operational capacity of a prototype catalytic module was determined experimentally, and a corresponding model correlation was developed and integrated into the GOTHIC containment code. This modified code was validated against experimental data. As an application, predictions of the effects, resulting from backfitting a large, dry PWR containment with 50 catalytic modules, were done using the modified code. The catalytic modules keep the hydrogen concentrations below a level of 10% where violent deflagrations could be expected. Local higher concentrations near the release location are inert due to associated low oxygen and high steam concentrations. A proper distribution of the modules in the containment guarantees full mixing of the atmosphere due to natural convective currents.