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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
April 2025
Latest News
Crash Course: The DOE’s Package Performance Demonstration
Inspired by a history of similar testing endeavors and recommended by the National Academy of Sciences and the Blue Ribbon Commission on America’s Nuclear Future, the Department of Energy is planning to conduct physical demonstrations on rail-sized spent nuclear fuel transportation casks. As part of the project, called the Spent Nuclear Fuel Package Performance Demonstration (PPD), the DOE is considering a number of demonstrations based on regulatory tests and realistic transportation scenarios, including collisions, drops, exposure to fire, and immersion in water.
Xuelong Fu, Zhengbo Ji, Chunbo Li
Nuclear Science and Engineering | Volume 191 | Number 1 | July 2018 | Pages 85-97
Technical Paper | doi.org/10.1080/00295639.2018.1449492
Articles are hosted by Taylor and Francis Online.
A novel neutron shielding B4C/CF/PI/AA6061 composite laminate (NSCL) with different layups containing 10 to 50 wt% of boron carbide (B4C) particles was successfully fabricated using a hot molding process. The effects of different B4C loadings and various configurations on the neutron transmission of the NSCLs were evaluated correspondingly. The MCNP 5.0 program was used to probe the neutron transmission mechanism of the NSCLs. The results showed that B4C particles are an effective absorbent, and neutron transmission of the NSCLs decreased with the increment of layups, B4C loadings, and the laminate thickness. Fast neutrons emitted from a 241Am-Be neutron source were first moderated by low atomic elements (hydrogen) and then absorbed by 10B nuclide contained in the B4C particles. Numerical simulation corroborated the experimental testing results.
