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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
Marzano sworn in as NRC commissioner
Matthew Marzano became the newest member of the Nuclear Regulatory Commission when he was officially sworn into office by chair Christopher Hanson this week.
The nuclear engineer and former reactor operator was confirmed last month in a 50–45 vote in the U.S. Senate. Last July, President Biden nominated Marzano to serve on the commission, which is tasked with formulating policies, developing regulations, issuing orders, and resolving legal matters.
Marzano’s term expires June 30, 2028.
Masafumi Nakatsuka
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 426-433
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34863
Articles are hosted by Taylor and Francis Online.
Embrittlement of Zircaloy fuel cladding tubes by corrosion media was studied from the viewpoint of its applicability to spent-fuel reprocessing. The results from irradiated as well as unirradiated tubes are summarized as follows: 1.When iodine was employed as the solute, the use of methanol as the solvent caused significant embrittlement of the Zircaloy. 2.For the iodine-methanol solution, the embrittlement increased with the iodine content but saturated at 1 wt%. 3.A water content of up to 10 vol% in the iodine-methanol solution did not decrease the extent of embrittlement. 4.Fracture was of the grain-boundary type, and a fuel cladding tube irradiated to ∼35 GWd/t showed the same embrittlement behavior as an unirradiated one.