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
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
Modernizing I&C for operations and maintenance, one phase at a time
The two reactors at Dominion Energy’s Surry plant are among the oldest in the U.S. nuclear fleet. Yet when the plant celebrated its 50th anniversary in 2023, staff could raise a toast to the future. Surry was one of the first plants to file a subsequent license renewal (SLR) application, and in May 2021, it became official: the plant was licensed to operate for a full 80 years, extending its reactors’ lifespans into 2052 and 2053.
D. Rochman, A. J. Koning, D. F. Da Cruz
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 323-338
Technical Paper | Fission Reactors/Fuel Cycle and Management | doi.org/10.13182/NT11-61
Articles are hosted by Taylor and Francis Online.
The effects of nuclear data uncertainties (cross sections, neutron emissions, fission yields, and decay data) on the burnup of a typical pressurized water reactor fuel element are presented in this paper. The uncertainties on reactivity swing, inventory, and radiotoxicity are obtained using a Monte Carlo method for nuclear data uncertainty propagation and the Monte Carlo transport code SERPENT. The impact of the nuclear data uncertainties for the two main actinide isotopes at the beginning of irradiation (235U and 238U) with the third and fourth most abundant actinide isotopes at the end of irradiation (236U and 239Pu) are calculated, showing the importance of fission yield data relative to transport data.