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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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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.
Charles W. Forsberg
Nuclear Technology | Volume 72 | Number 2 | February 1986 | Pages 121-134
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33735
Articles are hosted by Taylor and Francis Online.
A new type of boiling water reactor (BWR)—the process inherent ultimate safety (PIUS) BWR—has been conceived. A PIUS BWR is an advanced BWR that differs from the typical BWR in that a prestressed concrete reactor vessel (PCRV) with special internals replaces the conventional pressure vessel, emergency core cooling system, containment shell, spent fuel storage ponds, and most other components on the nuclear island. The reactor core and balance of plant are similar to current BWR designs. This approach effectively eliminates the possibility of reactor core meltdown and simplifies plant design. The PIUS BWR does not require operation of any mechanical or electrical components in any emergency for reactor shutdown or afterheat cooling, nor does it depend on any equipment outside the PCRV. The PCRV contains a natural circulation BWR; cool, borated water for emergency core cooling; a mechanism “X” that allows the cool, borated water to enter the reactor core if there is insufficient water in the core; and a mechanism “Y” that limits core power levels to available cooling capabilities.