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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
NRC issues subsequent license renewal to Monticello plant
The Nuclear Regulatory Commission has renewed for a second time the operating license for Unit 1 of Minnesota’s Monticello nuclear power plant.
R. A. Borrelli, Olivier Thivent, Joonhong Ahn
Nuclear Technology | Volume 174 | Number 1 | April 2011 | Pages 94-108
Technical Paper | Geochemistry and Ground Transport of RW | doi.org/10.13182/NT11-A11683
Articles are hosted by Taylor and Francis Online.
The study presented in this paper examines the potential of extruded bentonite as an additional barrier to radionuclide release to the far field. In the saturated repository, the bulk bentonite buffer surrounding the waste package will extrude into an intersecting fracture. Subsequent radionuclide release and transport into the fracture could be affected by the presence of this extrusion region. A model was previously established to describe the transport of radionuclides in the fracture that also includes this extruded bentonite. In this paper, we study model simulations for an idealized case of cesium transport through the extrusion region at elevated temperature. Extrusion speed will increase and cesium transport is enhanced with temperature; however, this extrusion region shows favorable performance in confining cesium at all temperatures. This study suggests that additional, rigorous modeling of this extrusion region as a barrier to radionuclide release with consideration of performance assessment studies is warranted.
