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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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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Fusion Science and Technology
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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.
Shigeo Numata, Yasuhiko Fujii, Makoto Okamoto
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 466-472
Technical Paper | Safety Environmental Aspect | doi.org/10.13182/FST91-A29387
Articles are hosted by Taylor and Francis Online.
Cleanup of tritiated water in typical reactor-size concrete enclosures is simulated taking into account the soaking of the tritiated water into the concrete. For an enclosure made of concrete with ordinary porosity, the “soaking effect” has little effect on the cleanup time for releases with tritium concentrations of <1 × 108 Bq/m3. If the concrete porosity is reduced to 0.03, the soaking effect has little effect on the cleanup time for a tritium concentration of up to 1 × 109 Bq/m3. An optimum flow rate of between 1 × 104 and 1.5 × 104 m3/h for the tritium removal system minimizes the costs of removal system equipment and facility downtime for releases with a concentration >5 × 108 Bq/m3 in a typical reactor-size enclosure. Estimated total costs to complete the cleanup within 48 and 72 h with these flow rates are within 1.3 times of the minimum total costs. The estimated total costs for a cleanup time of 48 h are comparable to those for a cleanup time of 72 h.