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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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!
Latest Magazine Issues
Dec 2024
Jul 2024
Latest Journal Issues
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.
Zhiyao Xing, Eugene Shwageraus (Univ of Cambridge)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 777-786
Prismatic block type Fluoride-salt-cooled High-temperature Reactors (FHRs) can benefit from Advanced Gas-cooled Reactor (AGR) technologies. To provide guidance for future AGR-like FHR design, this paper, based on systematic searches across a wide range of AGR-like assembly models and simplified single pin models, studies the beginning of cycle excess reactivity and coolant temperature coefficients of FHRs with different design parameters and alternative salt coolants. LiF-NaF-KF (FLiNaK) and non-Tritium-producing salt NaF-ZrF4 are studied as coolant options alternative to 2LiF-BeF2 (FLiBe) using unit cell models. The results suggest that the NaF-ZrF4 cooled, UC fuelled single pin models with 40% to 100% salt to graphite mass ratios and pitch to diameter ratios of 4.0 to 4.8 can achieve the best beginning of cycle neutronics performances among all designs options surveyed. While the assembly models and pin cell models capture the same reactor physics phenomena, designing FHR strictly within the physical constraint of AGR configuration limits the designs space and results in poorer neutronics performance comparing with the best performing unit cell models. Greater degrees of freedom could be considered in the future assembly level design process to best capture the desirable neutronics benefits of the recommended single pin designs.