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
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
Jiyun Zhao, Pradip Saha, Mujid S. Kazimi
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 174-190
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3834
Articles are hosted by Taylor and Francis Online.
The single hot-channel thermal-hydraulic stability model is expanded to investigate the effects of heat transport from fuel rods and to water rods on supercritical water-cooled reactor (SCWR) stability. Furthermore, the stability margin of the SCWR is compared with that of a typical boiling water reactor (BWR) by conducting a sensitivity study on operating conditions.The fuel thermal-dynamic effect is studied by coupling a lumped-parameter fuel model with the three-region coolant thermal-hydraulics model. It is found that the fuel heat capacity would dampen the oscillations in the coolant channel and therefore increase the stability of the system. Also, heating of the water rods, which could be allowed in the core, would improve single-channel stability.The stability sensitivity to power and flow rate conditions is analyzed for the U.S. reference SCWR design and compared with a typical BWR. The SCWR is found to be more sensitive to power and flow rate changes than the typical BWR. The water rod heating cannot significantly improve this sensitivity feature of the SCWR stability. The traditional stability measure of oscillation amplitude decay ratio does not capture the extent to which a stability margin exists in a particular design of the SCWR. The robustness of stability should be ascertained by examining accommodation of the potential variation and/or uncertainty about the nominal conditions.