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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.
Wei Shen, Dimitar Altiparmakov
Nuclear Science and Engineering | Volume 174 | Number 2 | June 2013 | Pages 109-134
Technical Paper | doi.org/10.13182/NSE12-42
Articles are hosted by Taylor and Francis Online.
This paper presents a multicell correction method that has been developed and implemented in the code suite WIMS-AECL/RFSP to capture the effects of the lattice-cell neighborhood while maintaining the basic structure of the single-cell-based reactor-physics methodology traditionally used for Canada Deuterium Uranium (CANDU)-reactor calculations for decades. To validate the effectiveness in treating the core-reflector interface heterogeneity as well as the checkerboard-voiding scenario, the results of WIMS-AECL/RFSP calculations (with and without the multicell correction) are compared with the results of MCNP5 full-core calculations for CANDU-type reactors. The presented results show that the multicell correction method is effective, generic, and capable of capturing the heterogeneity effects of the neighborhood in CANDU-type reactors.