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.
Roberto Bovalini, Francesco D’Auria, Antonio De Varti, Piero Maugeri, Marino Mazzini
Nuclear Technology | Volume 97 | Number 1 | January 1992 | Pages 113-130
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34630
Articles are hosted by Taylor and Francis Online.
The main results obtained at the University of Pisa on small-break loss-of-coolant accident counterpart experiments carried out in boiling water reactor (BWR) experimental simulators are summarized. In particular, the results of similar experiments performed in the PIPER-ONE, Full Integral Simulation Test (FIST), and ROSA-III facilities are analyzed. The tests simulate a transient originated by a small break in the recirculation line of a BWR-6 with the high-pressure injection systems unavailable. RELAP5/MOD2 nodalizations have been set up for these facilities and for the reference BWR plant. The calculated results are compared among each other and with the experimental data. Finally, the merits and the limitations of such a program are discussed in view of the evaluation of code scaling capabilities and uncertainty.
