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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
Yudai Tasaki, Akifumi Yamaji (Waseda Univ)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1144-1152
The concept of “multi-axial fuel shuffling” has been recently proposed for a high breeding core design of supercritical- water cooled reactor. In this study, the same design principle is applied to boiling water reactor (BWR) condition. The results show that the Compound System Doubling Time (CSDT) can be reduced by increasing fuel batch number of the upper blanket layer, but more investigations may be necessary to consider further improvement of the core breeding performance.
Moreover, fuel performance of the axially heterogeneous core has been evaluated with the power history obtained by the core calculations and modified FEMAXI-7 code which consider two different types of pellets (i.e., MOX and depleted uranium) within one fuel rod. The analysis results indicate that uncertainty in thermal conductivity of MOX pellets may be important in evaluating the peak pellet temperature, while relatively large plenum volume may be required at the bottom of the fuel rod to accommodate the large amount of fission gas release. Another potential design issue may be the cladding outer diameter increase by the MOX pellet swelling, which may have significant influence on evaluation of MCHFR.