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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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June 2025
Nuclear Technology
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.
Saerom Kwon, Satoshi Sato, Ryuta Kasada, Satoshi Konishi
Fusion Science and Technology | Volume 64 | Number 3 | September 2013 | Pages 599-603
Nuclear Systems: Analysis and Experiments | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST12-581
Articles are hosted by Taylor and Francis Online.
This study evaluates tritium production and breeding behavior in a LiPb blanket module with the neutron transport code MCNP using nuclear cross-section data from FENDL-2.1 libraries. The calculation results suggest that a sufficient tritium breeding ratio (TBR) can be obtained in the SiC-LiPb blanket concept and therefore a proper integral experiment on LiPb with DT neutrons can be planned for a small test module. Also, TBR, neutron shielding and nuclear heating in the module were evaluated. With the results of TBR and results from actual neutron generation devices, we have proposed a plan for an integral experiment with a measurable tritium amount.
