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.
M. Nakano, H. Tsunoda, J. Hirota
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 283-294
Technical Paper | doi.org/10.13182/NSE84-A17783
Articles are hosted by Taylor and Francis Online.
An experimental study has been made on FCA Assembly VIII-2 to test the validity of the calculational method for the reactivity effect due to axial displacement of fuel and cladding. The emphasis was placed on the systematic measurement of reactivity change and flux distribution in simple configurations rather than the simulation of a possible accident sequence. The analysis was made using the Japan Atomic Energy Research Institute Fast Set Version II. The transport calculation with an S4P0 approximation predicts both the reactivity change and the fission rates of 235U and 238U fairly well, although there still remains the trend of underestimation of reactivity effect, which increases with expansion of the fuel slumping to the core edge.
