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.
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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Jan 2025
Jul 2024
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Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Fermilab center renamed after late particle physicist Helen Edwards
Fermi National Accelerator Laboratory’s Integrated Engineering Research Center, which officially opened in January 2024, is now known as the Helen Edwards Engineering Center. The name was changed to honor the late particle physicist who led the design, construction, commissioning, and operation of the lab’s Tevatron accelerator and was part of the Water Resources Development Act signed by President Biden in December 2024, according to a Fermilab press release.
T. D. Bohm, B. Smith, M. E. Sawan, P. P. H. Wilson
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 703-707
Nuclear Analysis & Experiments | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12467
Articles are hosted by Taylor and Francis Online.
The surface source write/read capability in the 3-D neutronics code MCNP has been implemented in the CAD based DAG-MCNP. We performed neutronics calculations for a detailed solid model of an ITER first wall/shield module to assess the accuracy of the results obtained using the surface source for toroidal fusion systems. To further understand the sensitivity of the results to the size of the surface source and boundary conditions, we performed calculations for a simplified 3-D ITER model. The results show that use of the surface source approach is accurate provided that the surface source and associated reflective boundaries are extended beyond the component of interest by at least 10 cm and the surface source is generated/placed as close as possible to the front surface of that component.