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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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!
Latest Magazine Issues
Nov 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
Ryoichi Kurihara, Shuzo Ueda, Eisuke Tada
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1465-1469
Safety and Environment | doi.org/10.13182/FST96-A11963155
Articles are hosted by Taylor and Francis Online.
A vacuum vessel wall with a postulated crack is modeled by using the two-dimensional solid finite elements. The J-integral value, a criterion of fracture mechanics, is calculated to estimate the integrity of the vacuum vessel wall with a postulated crack.
The analytical results show that the J-integral value of a crack having a quarter depth of the wall width is considerably less than the fracture toughness JIC when the membrane stress is less than the 0.2% proof stress of the unirradiated material, even if the vacuum vessel is irradiated to 3 dpa. This means that a shallow crack in the vacuum vessel wall does not become critical in the design load.