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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
Hyunsuk Lee, Sooyoung Choi, Deokjung Lee
Nuclear Science and Engineering | Volume 180 | Number 1 | May 2015 | Pages 69-85
Technical Paper | doi.org/10.13182/NSE13-102
Articles are hosted by Taylor and Francis Online.
This paper proposes a new hybrid method combining the Monte Carlo (MC) method and the Method of Characteristics (MOC). The hybrid method employs MC and MOC together to solve a neutron transport problem. The two different methods are applied to different neutron energy ranges. The MC method is used to obtain accurate solutions in the resonance energy range, and the MOC is used for high and low neutron energy ranges to achieve high performance of the new method. The two methods are consistently coupled through scattering and fission source terms during the power iterations and group sweepings. Numerical tests with a model problem confirm that the hybrid method can produce a more accurate solution than a conventional MOC by a factor of 10 and much higher computational efficiency than a conventional MC method by a factor of 90.