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
Denver Airport may go nuclear
Colorado’s first nuclear power plant of the 21st century could be built at an unconventional site: the Denver International Airport (DEN).
In its mission to gain energy independence and become the greenest airport in the world, DEN has announced that it will conduct a feasibility study to determine the viability of building a small modular reactor on its 33,500-acre campus.
A. M. M. Ali, Hanaa H. Abou-Gabal, Nader M. A. Mohamed, Ayah E. Elshahat
Nuclear Science and Engineering | Volume 195 | Number 2 | February 2021 | Pages 203-213
Technical Paper | doi.org/10.1080/00295639.2020.1799604
Articles are hosted by Taylor and Francis Online.
This work aimed to develop accelerator-driven systems (ADSs) with a subcritical thorium assembly for fuel breeding and clean energy utilization by using several seed fuels. The ADS reactor core was loaded with three different fuel types, namely, reprocessed fuel, UN, and UO2 (seed fuel) associated separately with ThO2 fuel (blanket) in a heterogeneous approach. The Monte Carlo code MCNPX 2.7.0 has been employed to calculate neutronic parameters such as the effective multiplication coefficient (Keff), the nuclear fuel evolution during the burnup for every case, and the power fraction from seed and blanket fuels. The results indicate that the utilization of thorium (without any contents of 233U at the beginning of cycle) with reprocessed fuel allowed more 233U production than the UN and UO2 cases but with shorter cycle length. Introducing thorium fuel with the UN into the ADS core presented an efficient method to produce thermal power with the longest cycle length approaching 20 years.