ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Ontario eyes new nuclear development
A 1,300-acre site left undeveloped on the shores of Lake Ontario four decades ago could see new life as the home to a large nuclear facility.
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.