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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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
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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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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.
Yoshiyuki Asaoka, Kunihiko Okano, Tomoaki Yoshida, Ken Tomabechi
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 853-863
Fuel Cycle and Tritium Technology | doi.org/10.13182/FST96-A11963044
Articles are hosted by Taylor and Francis Online.
Requirements of tritium breeding ratio and the initial inventory of tritium for early fusion power reactors were investigated with a calculation model. The results of calculated time-dependence of tritium inventory were examined, in particular from the following three points of view; the doubling time of tritium inventory in the storage system to provide the initial inventory of the next plant, the recovery time in which the tritium inventory in the storage system recovers to the initial value and the minimum tritium storage required during the operation. The following limits were adopted to evaluate the results, i.e., the doubling time shorter than 3 years, the recovery time shorter than 1 year and the minimum storage larger than the tritium for 50 days bum up. For a reference case, which assumes reasonable performance parameters of the fuel processing subsystems, the requirements for the tritium breeding ratio and the initial tritium inventory were estimated to be 1.10 and 27.6 kg, respectively. If a poor tritium processing system is assumed, the requirements become inevitably higher. On the other hand, mitigation of the requirements is not conspicuous even with a good processing system. The obtained results suggest that the high performance tritium processing is indispensable, but still insufficient for achievement of tritium self-sufficiency. From the point of view of tritium fuel supply, a blanket system with high tritium breeding ratio is also indispensable in early stage of fusion power reactor development, in order to introduce fusion reactors at a reasonable pace.