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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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.