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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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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Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Satoshi Fukada, Shigenori Suemori
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 441-445
Other Concepts and Assessments | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-A13460
Articles are hosted by Taylor and Francis Online.
A system to utilize high-temperature nuclear heat effectively is proposed here. The system comprises a High-Temperature Gas-cooled nuclear Reactor (HTGR), reaction vessels to produce H2 using the steam-reforming reaction of CH4 or the Iodine-Sulfur (I-S) process, chemical heat pumps and He gas turbines. The chemical heat pumps are operated between the two decomposition temperatures of SO3 (~900°C) and HI (~500°C) of the I-S process. The pump system transfers heat from lower temperature to higher one with repeated H2 absorption-desorption cycles, and the overall thermal conversion ratio from H2O to H2 can be enhanced. The material candidate for H2 absorption in heat pump is considered TiH2 and ZrCoH3 (or UH3) according to the two reaction temperatures. The decomposition of the metal hydrides proceeds at their respective plateau pressures that are a function of temperature regardless of the H content in metals. Variations of the temperature and the equilibrium H2 pressure with repetitions of the heat-pump cycle are shown in the present paper comparatively. In addition, proton-conducting fuel cell system supplied with CH4 is incorporated in the high-temperature utilization system.
