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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Jacques Duco, Maria Trotabas
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 104-119
Technical Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27641
Articles are hosted by Taylor and Francis Online.
In the framework of the Organization for Economic Cooperation and Development/Committee on the Safety of Nuclear Installations Task Group on Three Mile Island Unit 2 (TMI-2), the Commissariat ??? I’Energie Atomique examined five samples retrieved from the damaged reactor core: a slightly damaged fuel rod chunk from assembly L1 of the core external row, a rod remnant in position C7 hanging from the assembly head, and three core bore rocks from both the ceramic and agglomerate regions of the damaged core. The analyses include visual observation, immersion density, metallography, wavelength dispersive X-ray analysis, X-ray diffraction, thermogravimetry, gamma spectroscopy, and neutron activation analysis. The information gained provides assessments of the maximum local temperatures reached during the accident, an insight into a possible fuel degradation mechanism for the rod in position C7, and information on fission product and control or structural material behavior. Such data, involving a small number of samples, will be added to those from other contributing laboratories to obtain an extensive data base, to try to understand the TMI-2 accident, and, presumably, to avoid the recurrence of a core melt on the basis of lessons to be learned.