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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
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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February 2023
Nuclear Technology
Fusion Science and Technology
Latest News
University of Florida–led consortium to research nuclear forensics
A 16-university team of 31 scientists and engineers, under the title Consortium for Nuclear Forensics and led by the University of Florida, has been selected by the Department of Energy’s National Nuclear Security Administration (NNSA) to develop the next generation of new technologies and insights in nuclear forensics.
Shuhei Nogami, Wenhai Guan, Akira Hasegawa, Makoto Fukuda
Fusion Science and Technology | Volume 72 | Number 4 | November 2017 | Pages 673-679
Technical Note | doi.org/10.1080/15361055.2017.1347463
Articles are hosted by Taylor and Francis Online.
The thermal and fatigue properties and the irradiation hardening of the potassium (K) doped tungsten (W) rods (20 mm in diameter) developed for fusion reactor divertor applications were investigated, and they were compared with the conventional hot-rolled W plates, which were previously reported. A part of the fatigue life of conventional hot-rolled W plate was newly obtained in this work. The K-doped W rod showed a few percent lower thermal conductivity than the conventional hot-rolled W plates. However, those values may meet the requirements of the ITER divertor application. The fatigue life at 500°C of the K-doped W rod was similar to the pure W plates at higher strain, whereas longer fatigue life of the K-doped W rod was observed at lower strain. The recrystallized K-doped W rod showed longer fatigue life at 500°C than the recrystallized pure W plates. The irradiation hardening level of the K-doped W rod was similar to the pure W plate after the irradiation up to 3 dpa at 500°C. Based on these evaluations of this work, the K-doped W rod in this work has similar or better properties than the conventional hot-rolled W plates under these particular test conditions though further evaluation and producing larger rods are desirable for the actual design and fabrication of the divertor.