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.
Explore membership for yourself or for your organization.
Conference Spotlight
2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
November 2025
Fusion Science and Technology
Latest News
Energy Secretary to speak at the 2025 ANS Winter Conference & Expo
In less than two weeks, the American Nuclear Society’s second annual conference of the year, the 2025 ANS Winter Conference & Expo, will come to Washington, D.C.
Today, ANS is announcing that Energy Secretary Chris Wright will be joining the list of nuclear leaders slated to speak at the conference.
Click here to register for the meeting, which will take place November 9–12 in Washington, D.C., at the Washington Hilton. Be sure to do so before November 7 to take advantage of priority pricing.
Kazuya Ohgama, Taira Hazama, Hiroki Katagiri, Atsushi Takegoshi, Tetsuya Mouri
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1336-1353
Research Article | doi.org/10.1080/00295450.2023.2295168
Articles are hosted by Taylor and Francis Online.
In the prototype fast breeder reactor Monju, reaction rate distributions of the fission reaction rates of 239Pu, 235U, and 238U and the capture reaction rate of 238U were measured using activation foils during its system startup test. The measurements in the core and radial blanket regions were evaluated in detail, and their reliability and usefulness as the validation data for fast reactor neutronics design methodologies were examined through a comparison with calculations. The reaction rate data measured in Monju were confirmed all reliable and useful as the validation data. The fission reactions of 239Pu, 235U, and 238U can be validated with an accuracy of a few percent in the core and blanket regions. The capture reaction of 238U in the core region also can be validated with a similar accuracy, whereas a precise calculation of the foil cross section is necessary to consider the resonance shielding effects of the surrounding fuel pins and a foil.