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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Nuclear Technology
Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Francesco Ghezzi, Natesan Venkataramani, Andrea Conte, Giovanni Bonizzoni, W. T. Shmayda
Fusion Science and Technology | Volume 27 | Number 4 | July 1995 | Pages 458-475
Technical Paper | Tritium System | doi.org/10.13182/FST95-A30364
Articles are hosted by Taylor and Francis Online.
Experimental investigation of the reaction of light and heavy water vapors with a metallic alloy and the release of hydrogen by batch-mode conversion with a Zr(V0.5Fe0.5)2 getter is presented. The dependence of cracking of water vapor on the alloy temperature and water vapor pressure is studied. The roles of initial as well as increasing concentrations of hydrogen and oxygen in the alloy are delineated. The conversion rate constant is observed to shift from being surface dissociation process-dependent to bulk diffusion process-dominated during the conversion process. Hydrogen sorption in the alloy and its release during the batch conversion of water vapor, which assumes considerable significance from the perspective of recovering tritium as fuel gas from tritiated water waste, are discussed based on the studies performed that maintained the getter at various temperatures in the range of 100 to 400°C and over a water vapor pressure range of 50 to 500 Pa, with various hydrogen and oxygen concentrations in the getter alloy.