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
Nov 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
November 2025
Fusion Science and Technology
Latest News
Nuclear News 40 Under 40: The wait is over
Following the enthusiastic response from the nuclear community in 2024 for the inaugural NN 40 Under 40, the Nuclear News team knew we had to take up the difficult task in 2025 of turning it into an annual event—though there was plenty of uncertainty as to how the community would receive a second iteration this year. That uncertainty was unfounded, clearly, as the tight-knit nuclear community embraced the chance to celebrate its up-and-coming generation of scientists, engineers, and policy makers who are working to grow the influence of this oft-misunderstood technology.
Gunji Nishio, Noboru Yamazaki
Nuclear Technology | Volume 102 | Number 2 | May 1993 | Pages 232-251
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT93-A34819
Articles are hosted by Taylor and Francis Online.
The FACE computer code was developed to calculate postulated solvent fire behavior in the extraction process of a nuclear fuel reprocessing plant. The FACE code calculates temperature, pressure, and off-gasflow rate by one- and two-dimensional thermofluid analyses. The code uses this information to evaluate the safety of the associated air ventilation system as demonstrated by its ability to confine the fire-generated radioactive particles by transport, deposition, and filtration of smoke. The mathematical models in FACE were verified by comparison of FACE calculations with the results of Japan Atomic Energy Research Institute fire demonstration tests simulating a hypothetical solvent fire accident in the extraction process.
