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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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
Marzano
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.
August W. Cronenberg, E. L. Tolman
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 273-282
Technical Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27654
Articles are hosted by Taylor and Francis Online.
Inspection of the Three Mile Island Unit 2 (TMI-2) reactor vessel has yielded a wealth of information on core melt debris thermal interactions with vessel internal structures. The observed damage state of such structures is summarized and an analysis is presented to further the understanding of governing physical processes. Specifically, thermal damage is assessed for the baffle plates surrounding the core periphery, the core former plates, the bottom head instrument penetrations, and the lower head. Analysis indicates that differences in damage characteristics to such structures are due largely to differences in contact time with molten corium, the heat capacity of the various structures, and exposure to coolant. Vessel and debris examinations corroborate the present understanding of melt debris/structural interactions during the melt relocation phase of the TMI-2 accident.