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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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!
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Latest News
EnergySolutions to help explore advanced reactor development in Utah
Utah-based waste management company EnergySolutions announced that it has signed a memorandum of understating with the Intermountain Power Agency and the state of Utah to explore the development of advanced nuclear power generation at the Intermountain Power Project (IPP) site near Delta, Utah.
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.