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.
J. E. Houghtaling, J. E. Grund
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 412-426
Technical Paper | doi.org/10.13182/NSE69-A18738
Articles are hosted by Taylor and Francis Online.
Reactor kinetics investigations have been performed for cold-start-up, hot-start-up, hot-standby, and operating-power reactivity accidents using the UO2-fueled, pressurized-water type SPERT-III reactor. Power excursion behavior was predicted for every SPERT-III experiment by digital computer calculations using the SPERT-developed PARET code. Extrapolations for severe cold-start-up excursion consequences were obtained from severe transient tests on SPERT-III fuel samples in the SPERT-IV capsule driver core. Analyses of the SPERT-III data show that prompt moderator heating was as significant as the Doppler effect in limiting the magnitude of power excursions in the SPERT-III core at operating temperatures. Comparisons of calculations and experimental data demonstrate that PARET is capable of predicting power excursion behavior in SPERT-III within experimental uncertainty for the range of conditions investigated. The SPERT-III integral-core tests also provide a broad base of experimental data for demonstrations of the capabilities of other existing models in predicting non-damaging power excursion behavior in UO2-fueled reactors.