ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Dec 2024
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Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
H. Oomura, M. Akiyama, K. Hiya
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 625-629
Blanket and First-Wall Engineering | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40109
Articles are hosted by Taylor and Francis Online.
The lifetime evaluation study for a fusion reactor first wall was performed using newly developed one-dimensional analysis code. Since the in-vessel components are exposed to a severe and complex environment, the evaluation of their lifetime is required for the design of fusion reactors. In the present paper, the first wall was assumed to be a flat plate and free to expand but not bend. Linear fracture mechanies was used to investigate the crack growth behavior and parametric surveillance was performed changing the swelling rate, initial crack length and wall loading. It is concluded that 1) the crack growth from the plasma side will limit the lifetime of the first wall, and 2) fracture toughness and initial crack length are the most important limiting factors for the first wall lifetime.